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TECHNICAL REPORTS SERIES No. 273
Handbookon Nuclear Activation Data
INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1987
HANDBOOKON NUCLEAR ACTIVATION DATA
The following States aie Members of the International Atomic Energy Agency:
AFGHANISTANALBANIAALGERIAARGENTINAAUSTRALIAAUSTRIABANGLADESHBELGIUMBOLIVIABRAZILBULGARIABURMABYELORUSSIAN SOVIET
SOCIALIST REPUBLICCAMEROONCANADACHILECHINACOLOMBIACOSTA RICACOTE D'lVOIRECUBACYPRUSCZECHOSLOVAKIADEMOCRATIC KAMPUCHEADEMOCRATIC PEOPLE'S
REPUBLIC OF KOREADENMARKDOMINICAN REPUBLICECUADOREGYPTEL SALVADORETHIOPIAFINLANDFRANCEGABONGERMAN DEMOCRATIC REPUBLICGERMANY, FEDERAL REPUBLIC OFGHANAGREECE
GUATEMALAHAITIHOLY SEEHUNGARYICELANDINDIAINDONESIAIRAN, ISLAMIC REPUBLIC OFIRAQIRELANDISRAELITALYJAMAICAJAPANJORDANKENYAKOREA, REPUBLIC OFKUWAITLEBANONLIBERIALIBYAN ARAB JAMAHIRIYALIECHTENSTEINLUXEMBOURGMADAGASCARMALAYSIAMALIMAURITIUSMEXICOMONACOMONGOLIAMOROCCONAMIBIANETHERLANDSNEW ZEALANDNICARAGUANIGERNIGERIANORWAYPAKISTANPANAMA
PARAGUAYPERUPHILIPPINESPOLANDPORTUGALQATARROMANIASAUDI ARABIASENEGALSIERRA LEONESINGAPORESOUTH AFRICASPAINSRI LANKASUDANSWEDENSWITZERLANDSYRIAN ARAB REPUBLICTHAILANDTUNISIATURKEYUGANDAUKRAINIAN SOVIET SOCIALIST
REPUBLICUNION OF SOVIET SOCIALIST
REPUBLICSUNITED ARAB EMIRATESUNITED KINGDOM OF GREAT
BRITAIN AND NORTHERNIRELAND
UNITED REPUBLIC OFTANZANIA
UNITED STATES OF AMERICAURUGUAYVENEZUELAVIET NAMYUGOSLAVIAZAIREZAMBIAZIMBABWE
The Agency's Statute was approved on 23 October 1956 by the Conference on the Statute of theIAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. TheHeadquarters of the Agency are situated in Vienna. Its principal objective is "to accelerate and enlarge thecontribution of atomic energy to peace, health and prosperity throughout the world".
© IAEA, 1987
Permission to reproduce or translate the information contained in this publication may be obtainedby writing to the International Atomic Energy Agency, Wagramerstiasse 5, P.O. Box 100, A-1400 Vienna,Austria.
Printed by the IAEA in Austria
April 1987
TECHNICAL REPORTS SERIES No. 273
HANDBOOKON NUCLEAR ACTIVATION DATA
INTERNATIONAL ATOMIC ENERGY AGENCYVIENNA, 1987
HANDBOOK ON NUCLEAR ACTIVATION DATAIAEA, VIENNA, 1987
STI/DOC/10/273ISBN 92-0-135087-2
FOREWORD
More than a decade has passed since the Handbook on Nuclear ActivationCross-Sections (Technical Reports Series No. 156) was issued. This publication wasfavourably received by scientists working in the fields of education and industrialapplications, as well as in basic research, and there have been many requests sincethen for a more up to date version. In response to these requests, and with theendorsement of the International Nuclear Data Committee of the IAEA, this newTechnical Report, Handbook on Nuclear Activation Data, is being issued for the par-ticular benefit of the many scientists who use nuclear activation methods.
The preparation of such a handbook requires a number of compromises whichmay not be acceptable to everyone. The scope and treatment of each topic had to belimited in order to be concise and this limit may conflict with the wishes of readersinterested in greater detail. However, the material in this Handbook is generallysimilar to that contained in the earlier version, though there are several importantdifferences, besides the inclusion of more recent data. In Part 1-1, all necessaryinformation on standard reference data has been assembled, something that wasmissing in the previous Handbook. Great efforts have been made to include as muchrecent information as possible. There is, however, one important omission. TheENDF/B-VI Standards File has not as yet been released and thus evaluated data fromthe ENDF/B-V Standards File have been quoted, together with up to date statusreports. This part will almost certainly have to be revised when the ENDF/B-VIStandards File becomes available.
The contents of this Handbook are divided into four parts, i.e. standardreference data and neutron, charged particle and photonuclear activation data. Theneutron source and gamma ray standards data in Part 1 and the californium spectrumaveraged data in Part 2 have been added following requests by the users of theprevious Handbook.
While every effort has been made to ensure consistency and uniformity ofpresentation between the different parts of this Handbook, there remain someinconsistencies concerning the standard reference values of some half-life, abundanceand other data that are quoted. The reader is therefore requested to refer to Part 1-1for appropriate citations.
The emphasis in this Handbook is on evaluated or recommended values ratherthan on an exhaustive presentation of all experimental results. This aim has been onlypartially achieved because in some cases it has not been possible to make a selectionbetween parallel presentations of different results. A number of valuable suggestionsfor subjects to be included in this Handbook have been received and most of themhave been adopted; it is hoped that those subjects not included, such as PIXE, canbe considered in a separate publication.
It should be emphasized that many of the data contained in this Handbook havebeen assembled in special computer files in order to ease their updating and tofacilitate their use in computations. These files are being updated continuously andcan be obtained from the IAEA Nuclear Data Section upon request.
The Agency wishes to thank all of the contributors and also those who havecritically reviewed the original manuscripts, especially H. Conde", A.B. Smith andA.D. Carlson for Part 1-2, and H. Vonach for Parts 2-2 and 2-3. The IAEA officerresponsible for the planning, overall co-ordination between the authors and for theorganization of this Handbook was K. Okamoto.
EDITORIAL NOTE
The papers have been edited by the editorial staff of the IAEA to the extent considered necessaryfor the reader's assistance. The views expressed remain, however, the responsibility of the namedauthors or participants. In addition, the views are not necessarily those of the governments of thenominating Member States or of the nominating organizations.
Although great care has been taken to maintain the accuracy of information contained in thispublication, neither the IAEA nor its Member States assume any responsibility for consequences whichmay arise from its use.
The mention of names of specific companies or products (whether or not indicated as registered)does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsementor recommendation on the part of the IAEA.
The authors are responsible for having obtained the necessary permission for the IAEA toreproduce, translate or use material from sources already protected by copyrights.
CONTENTS
PART 1. STANDARD REFERENCE DATA
1-1. Nuclear properties 3J.K. Tuli1. Introduction 32. Explanation of symbols used in table 4
2.1. Column 1. Isotope (Z, El, A) 42.2. Column 2. T% or abundance 42.3. Column 3. Decay mode 4
References 5Table I: Nuclear properties of all known nuclides and some of their
isomeric states 6
1-2. Standard monitor reactions for neutrons 29Z. Body1. Introduction 292. The 'H(n,n)'H cross-section 30
2.1. Status 353. The 3He(n,p)3H cross-section 35
3.1. Status 374. The 6Li(n,t)4He cross-section 40
4.1. Status 405. The 10B(n,a)7Li, loB(n,ao)
7Li and 10B(n,a,)7Li* cross-sections 415.1. Status 44
6. The C(n,n)C cross-section 456.1. Status 45
7. The 27Al(n,a)24Na cross-section 507.1. Status 51
8. The ^Fefn.p^Mn cross-section 518.1. Status 57
9. The 197Au(n,7)198Au cross-section 64
9.1. Status 6410. The ^Ufof) cross-section 73
10.1. Status 7311. The 238U(n,f) cross-section 76
11.1. Status 77References 78
Neutron Source Standards
1-3. Production of monoenergetic neutrons between 0.1 and 23 MeV:Neutron energies and cross-sections 83M. Drosg, O. Schwerer1. Introduction 832. Selection of the appropriate source 84
2.1. Neutron source intensity 852.2. Neutron background and target structure 89
2.2.1. Gas targets 923. Parametrization of the differential cross-sections 93
3.1. Interaction of protons with tritons 953.1.1. 3H(p,n)3He 953.1.2. 'H(t,n)3He 98
Graphs of the 3H(p,n)3He reaction 99Graphs of the 'H(t,n)3He reaction 107
3.2. Interaction of deuterons with deuterons I l l3.2.1. 2H(d,n)3He I l l
Graphs of the 2H(d,n)3He reaction 1153.3. Interaction of deuterons with tritons 121
3.3.1. 3H(d,n)4He 1213.3.2. 2H(t,n)4He 124
3.4. Interaction of protons with 7Li 126Graphs of the 3H(d,n)4He reaction 129
3.4.1. ^ ( p . n / B e and 7Li(p,n,)7Be* 1383.4.2. ' H ^ L l n / B e and 'H^Li.n^Be* 138
Graphs of the 2H(t,n)4He reaction 139Graphs of the 7Li(p,n)7Be reaction 145Graphs of the 'H(7Li,n)7Be reaction 153
Appendix 158References 161
Neutron Source Standards
1-4. The neutron spectrum of spontaneous fission of californium-252 163W. Mannhart1. Introduction 1632. Status of data for the neutron spectrum 1643. Evaluation of the neutron spectrum by least squares methods 165
3.1. Principles of the least squares adjustment 1653.2. Data on spectrum averaged neutron cross-sections 1663.3. Prior information on the neutron spectrum 1673.4. Energy dependent cross-section data 171
4. Results of the evaluation of the spectral distribution 1725. Comparison with other experimental and theoretical data 1756. Conclusions 182References 183
1-5. Decay data for radionuclides used as calibration standards 187A. Lorenz1. Introduction 1872. Selection of standards included in the file 1873. Selection of recommended gamma ray energies and intensities 1884. Key to the comments column in the table 188Table I: Photon energies and emission probabilities for radionuclides
used as standards 189References 195
PART 2. NEUTRON ACTIVATION
2-1. Thermal neutron cross-sections and infinite dilution resonanceintegrals 199E. Gryntakis, D.E. Cullen, G. Mundy1. Introduction 1992. Definition of a resonance integral 2003. Experimental measurement with a Cd filter 202
3.1. The Westcott method 2023.2. The common method 204
4. Experimental measurement without a Cd filter 2055. Explanation of the columns in Table II 248References 248Annex: Effective resonance energy values 256F. De ComReferences to the Annex 260
2-2. Data for 14 MeV neutron activation analysis 261Z. Body, J. Csikai1. Introduction 2612. The activation process 2623. Explanation of the nuclear data in Table II 3004. Explanation of the cross-section tables 301References 303
2-3. Activation cross-sections induced by fast neutrons 305V.N. Manokhin, A.B. Pashchenko, V.I. Plyaskin, V.M. Bychkov,V.G. Pronyaev1. Introduction 3052. Procedure for file preparation 3063. Presentation of the data 3064. Relationships with other sections of this Handbook 307References 308Graphs of the reactions 309
2-4. Californium-252 spectrum averaged neutron cross-sections 413W. Mannhart1. Introduction 4132. Basis of the experimental data 414
2.1. Experiments with incomplete uncertainty information 4142.1.1. Experiment by Pauw and Aten 4142.1.2. Experiment by Kirouac et al 4142.1.3. Experiment by Green 4222.1.4. Experiments by Csikai et al 4222.1.5. Experiment by Benabdallah et al 4232.1.6. Experiments by Dezso and Csikai with
improved experimental conditions 4232.2. Experiments with complete uncertainty information 424
2.2.1. Experiments performed at the Physikalisch-TechnischeBundesanstalt (PTB) 424
2.2.2. Fission cross-section measurements at the NBS 4252.2.3. Measurements by Adamov et al 4262.2.4. Measurements by Spiegel et al 4262.2.5. Measurements by Davis and Knoll 4282.2.6. Measurements by Winkler et al 4282.2.7. Measurements by Kobayashi et al 4282.2.8. Measurements by Mannhart 4282.2.9. Measurements by Lamaze et al 430
2.3. Other data 4313. Calculation of spectrum averaged cross-sections 4314. Evaluation of a 'best' set of experimental data 432References 435
PART 3. CHARGED PARTICLE ACTIVATION
3-1. Calculation of excitation functions for charged particle inducedreactions 441R. Nowotny, M. Uhl1. Introduction 4412. Models and parameters 443
2.1. Reaction mechanisms and their importance for activationproduct cross-sections 443
2.2. The compound nucleus evaporation model 4442.3. Models for pre-equilibrium emission 449
2.3.1. The exciton model 4492.3.2. The hybrid model 452
2.4. Auxiliary quantities and model parameters 4542.4.1. Transmission coefficients 4542.4.2. Level densities 4562.4.3. Pre-equilibrium model parameters 457
3. Computer codes 4604. Applications 461
4.1. Proton induced reactions 4624.1.1. 67Ga 4634.1.2. 77Kr 4634.1.3. 127Xe 4664.1.4. 123Xe 4694.1.5. 201Pb 469
4.2. Yield calculations 4704.3. Reactions with particles other than protons 471
5. Conclusions 473References 474
3-2. Activation cross-sections for elements from lithium to sulphur 479P. Albert, G. Blondiaux, J.L. Debrun, A. Giovagnoli, M. Valladon1. Introduction 479Tables of the reactions 479Graphs of the cross-sections 490References 534
3-3. Thick target yields for the production of radioisotopes 537P. Albert, G. Blondiaux, J.L. Debrun, A. Giovagnoli, M. Valladon1. Introduction 537Tables of the reactions 538Graphs of the thick target yields 562References 626
PART 4. PHOTONUCLEAR ACTIVATION
4-1. Photonuclear cross-sections 631B. Forkman, R. Peters son1. Introduction 6312. Bremsstrahlung reaction yield 6313. Comments 635References to Sections 1 through 3 6354. Contents list of graphs 636Graphs of the reactions 637References to Section 4 808
Part 1
STANDARD REFERENCE DATA
1-1. NUCLEAR PROPERTIES*
J.K. TULI**National Nuclear Data Center,Brookhaven National Laboratory***,Upton, New York,United States of America
Abstract
NUCLEAR PROPERTIES.The paper presents half-life, abundance and decay modes for all known nuclides and
some of their isomeric states. The data are taken from the 1984 edition of the EvaluatedNuclear Structure Data File maintained by the National Nuclear Data Center at BrookhavenNational Laboratory.
1. INTRODUCTION
Half-life, abundance and decay modes for all known nuclides and some oftheir isomeric states are presented in Table I. The nuclides for which none of thesethree properties are known have been omitted. The data given here are from theadopted properties of the various nuclides as given in the 30 Nov. 1984 edition of theEvaluated Nuclear Structure Data File (ENSDF), a computer file of evaluatedexperimental nuclear structure data maintained by the National Nuclear DataCenter at Brookhaven National Laboratory, Upton, New York. The data inENSDF are based on experimental results for A = 45 to 263 [ 1 ] and in Nuclear Physicsfor A < 45. For those nuclides for which either there is no data in ENSDF or morerecent data are available, the half-lives and decay modes are taken from Ref. [2].In some cases, the percentage decay modes are taken from material in Ref. [3].Recent data, contained in Refs [4-16], have also been included. The isotopicabundances are those of Holden, Martin and Barnes [17]. Other references,experimental data and information on the data measurements can be found in theoriginal evaluations contained in Ref. [1] and in Nuclear Physics.
* The nuclear properties given here are based upon the author's pocket-size handbook -Nuclear Wallet Cards (1985) — published and distributed free by the National Nuclear DataCenter, Brookhaven National Laboratory, Upton, New York, 11973, USA. Other quantitiescontained in the Nuclear Wallet Cards and not presented here are spin, parity, mass excess anda number of appendices.** This research was supported by the Office of Basic Energy Sciences, US Department of
Energy.*** Operated by Associated Universities, Inc., under contract with the US Department ofEnergy.
4 TULI
2. EXPLANATION OF SYMBOLS USED IN TABLE
2.1. Column 1. Isotope (Z, El, A)
Nuclides are listed in order of increasing atomic number (Z) and aresubordered by increasing mass number (A). Included are all isotopic species, allisomers with half-life >\ s and other selected well known isomers. The nuclidesfor which neither the half-lives nor the decay modes are known have been omitted.
Isomeric states are denoted by the letter 'm' after the mass number and aregiven in order of increasing excitation energy. More than one entry for a nuclide,without the letter 'm' for any of them, indicates that their relative excitationenergies are not known.
The symbols Rf (rutherfordium) and Ha (hahnium) have been used forelements with Z = 104 and 105, respectively. However, these have not beenaccepted internationally owing to conflicting claims of their discovery.
2.2. Column 2. T] /2 or abundance
The half-life and the abundance are given followed by units (the %in the case of the abundance), followed by the uncertainty, in italics.The uncertainty given is in the last significant figures. For example,8.1 s 10 means TI/2 = 8.1 ± 1.0 s. For some very short-lived nuclei, level widthsrather than half-lives are given. In these cases also the width is followed by theunits (e.g. eV, keV or MeV), which are followed by the uncertainty, in italics,if known. Those half-life values for which there is no uncertainty given are takenfrom Ref. [2] and the uncertainty in most of these cases is < 5 in the last figuregiven.
2.3. Column 3. Decay mode
Decay modes are given followed by the per cent branching, if known ('w'indicates a weak branch). The decay modes are given in decreasing strength fromleft to right. The percentage branching is omitted where there is no competingmode of decay.
The various modes of decay are:
/3- 0 - decay;£ £ (electron capture) ort+|3+ or/3+ decay;IT Isomeric transition (through y or conversion-
electron decay);n, p , oc, ... Neutron, proton, alpha, ... decay;SF Spontaneous fission;
PART 1-1
2/3-, 3a, ... Double 0 - decay (|3-/?-), decay throughemission of 3 a's, ...;
0-n , j3-p, j3-a, ... Delayed n, p, a, ..., emission following/3- decay;
£p,£a, Delayed p, a,SF, ... decay following£SF, ... E or/3+ decay.
REFERENCES
[ 1] TULI, J.K., (Ed.), Nucl. Data Sheets B7-46 (1972M1985).[2] Chart of the Nuclides, 13th edn (WALKER, F.W., MILLER, D.G., FEINER. F., Eds),
Knolls Power Laboratory, Schenectady, NY (1983).[3] BROWNE, E., et al., Table of Isotopes, 7th edn (LEDERER, CM., SHIRLEY, V.S. Eds),
Wiley, New York (1978).[4] ALBURGER, D.E., private communication on 18OmTa, 1984.[5] FREKERS, D., et al., Half-life of ""Ti, Phys. Rev. C 28 (1983) 756.[6] KUTSCHERA, W., et al., Half-life of 60Fe, Nucl. Instrum. Methods BS (1984) 430.[7] ROSE, H.J., JONES, G.A., A new kind of natural radioactivity, Nature (London) 307
(1984)245. (223Ra)[8] LANGEVIN, M., et al., Observation of (3-delayed triton emission, Phys. Lett. 146B
(1984) 176. (nLi)[9] Recent half-life measurements on 156Pr, 163Gd, I6sTb, 168Dy, carried out at the Idaho
National Engineering Laboratory, as reported in the literature.[10] LANGEVIN, M., et al., Nucl. Phys. A414 (1984) 151. (32~3SNa, "^ '"^Mg)[11] DETRAZ, C, et al., Phys. Rev. C 19(1984) 164. (29Mg, 31A1)[12] GUILLEMAUD-MUELLER, D., et al., Nucl. Phys. A426 (1984)37. (32A1)[13] MURPHY, M.Y., Phys. Rev. Lett. 49 (1982) 455. (32A1)[14] KAITA, R., et al., Nucl. Phys. A344 (1980) 389. (32Si)[15] ELMORE, D., et al., Phys. Rev. Lett. 45 (1980) 589. (32Si)[16] VOSICKI, B., et al., Nucl. Instrum. Methods 186 (1981) 307. (42'43C1)[17] HOLDEN, N.E., MARTIN, R.L., BARNES, I.L., Isotopic composition of the elements
1983, Pure Appl. Chem. 56 (1984) 675.
QZ
ooWQ
UPZ
z
OooUJHCM
PH
oOHPH
OH
w_)up
zwpa<H
00pqH
HooU
2W53O00M
OH
1HUH
oso00
CO.
Q a . o a . Q a . ^ 2 . w w w
! e ^t'-^.°><~'»~.
: « " » : » ,= -<•* " • - ° c
O
co f in CD r-co o
I I I I I - «
00 v
OK•inoco
^4I I I
^ C N , ^ ^ c ^ '
CO i n t o • c o '
D-H to t-- oo co o -H c\j t-- oo en o -H OJ co •* m oo co o -* cy co •**• in to —< OJ co •* in to t-- co OJ CO •«*• in to i> oo co o —< into
ca o ^ o t«-OQ
m to oo o>
PART 1-1
IsotopeZ
14
15
16
17
18
19
El
Si
P
S
Cl
Ar
K
A
27282930313233342628293031323334353629303132333435363738393132
333434m3536373838m39404142433233343536373839404142434445463536373838m39
Tl/2 orAbundance
4.16 s92.23%4.67%3.10%2.62 h105 y
6.11 s2.77 s
20 ms270.3 m4 142 s2.498 m
100%14.26 d
25.34 d12.43 s47.3 s5.9 s
0.187 s1.24 s
2.584 s95.02%0.75%4.21%
87.51 d0.02%
5.05 m2.84 h11.5 s0.15 s
298 ms
2.511 s1.5262 s32.23 m75.77%
3.01-105
24.23%37.24 m715 ms55.6 m1 35 m34 s .6.8 s3.3 s0.1 s
173 ms845 ms1.775 s0.337%
35.04 d0.063%269 y
99.600%1.827 h32.9 y5.37 m11.87 m
21.48 s8 s /
0.19 s342 ms1.226 s
7.636 m924.6 ms93.25817
21
1113
2120
i 5154
4128
7
441891812
121
2
325145y 255
322
?32
234
341
337
116515
27181530
Decay Mode
£
0-0-P-0-z, cp, £2p?£
£
0-p-p-0-0-£, £P££
P-P~P-0"£, £p£, £p=0.007%,£0=0.01%£££53.1%, IT46.9%
0-98.1%, £ 1.9%
IT0-0-0-
£, £p£ , £p 34%££
£
0"
0-P-0-0-0-0-£, £P£, £p, £0£z£
IsotopeZ
19
20
21
22
23
El
K
Ca
Sc
Ti
V
A
40
41424344454647484950515336373839404142434445464748
4950515340414243m434444m4545m4646m4748495050m514142434445464748495051525344454647
Tl/2 orAbundance
1.277-10'0.0117%6.7302%
r30
12.360 h 322.3 h
22.13 n17.3 n107 s17.5 s6.9 s1.3 s
472 ms365 ms30 ms0.1 s
175 ms447 ms
859.6 ms96.941%
1.03-10s
0.647%0.135%2.086%
163.8 d0.004%
4.535 ed0.187%
8.716 n13.9 s
10 s90 ms
182.3 m596.3 us681.3 m61.6 s
3.891 h3.927 h58.6 h
100%0.32 S
83.83 d18.70 s3.345 d43.7 h57.4 m
1.710 a0.35 s12.4 s80 ms199 ms513 ms54.2 y3.08 h
8.0%7.3%
73.8%5.5%5.4%
5.76 m1.7 m
32.7 s90 ms539 ms
422.33 in32.6 n
119603
2
455
310
1413y *3351834
111
e5
7
n» 741281
1253/
a3i
2
e8211
1
119
1518
• 203
Decay Mode
0-89.3%, £ 10.7%
0-0-0-0-0-P-0-0", 0-n0-, 0-n 29%0-,/Hi0-,0-n£, £P
z'f
E
0-
0-
0-
f"£p££
££IT 98.8%, c 1.2%
ITP-IT0-P-
IT98.7%, 0- 1.3%0-£, £p£££f
0-P~-£, £0£
£
TABLE i (cont.)
TULI
IsotopeZ El A
Tl /2 orAbundance Decay Mode
23 V 48 15.974 d 3 £49 330 d (5 £50 1 .5 -10" y +3-7 £>70%, 0-<3O%
0.250% 251 99.750% 252 3.75 m I 0-53 1.61 m 4 0-54 49.8 s 5 0-55 6.54 s 15 0-
24 Cr 45 50 ms 6 z, £p>25%46 0.26 s 6 E, £p47 508.0 ms 10 £48 21.56 h 3 £49 42.09 m 15 c50 4.345% 951 27.704 d 4 £52 83.789% 1253 9.501% II54 2.365% 555 3.497 1 3 0-56 5.94 m 10 0-57 21 s 0-
25 Mn 49 0.38 s £50 283.0 ms 4 £50m 1.75 m 3 z51 46 .2 m I £52 5.591 d 3 £52m 21 .1 m 2 z 98.32%,
IT 1.75%53 3 . 7 - 1 0 6 y 4 £54 312 .5 d 5 £55 100%56 2.5785 h 6 0 -57 1.45 m 0 -58 6 5 . 3 s 7 0 -58m 3 .0 s / 0 -59 4 . 6 s / 0 -60 1.79 s 10 0 -62 0 .9 s 0 -
26 Fe 49 75 ms 10 z, £p51 0.25 s £52 8.275 h 8 z52m 46 s 2 £ 80%, IT 20%53 8.51 m 2 z53m 2.58 • ! IT54 5.8% I55 2.68 y £56 91.72% 3057 2.2% I58 0.28% ;59 44.496 d 7 0-60 1.49-106 y 27 0-61 5.98 m 6 0-62 68 s 2 0-63 4.9 s 0-
27 Co 53 262 ms 25 z53m 0.25 s £ 98.5%, pa: 1.5%54 193.23 ms 14 z54m 1.48 m 2 z55 17.53 h 3 £56 78.76 d 12 z57 270.9 d 6 z58 70.916 d 15 z58m 9 .15 h 10 IT59 100%60 5.271 y I 0-
Isotope Tl/2 orZ El A Abundance
27 Co 60m 10.47 m 4
28 Ni
29 Cu
30 Zn
616262m636453555657585960616263646566676857585960616263646566676868m697070m7172735758596061626364656667686969m
707171m7273747576777879
1.650 h 51.50 m 4
13.91 m 527.4 s 50.30 s 345 ms (5189 ms 56.10 d 2
36.08 h 968.27% I
7.5-10 4 y 1326.10% I1.13% i3.59% I
100.1 y 200.91% /
2.520 h 254.6 h 4
21 S 1
0.18 s ?3.204 s 781.5 s 523.2 n 3
3.408 h 109.74 m 269.17% 2
12.701 h 230.83% 25.10 m 261.92 h 9
31 s I3.75 m 53.0 m I4.5 s 146 s 520 s
6.6 s3.9 s
40 ms 10
183.7 ms 232.38 m 589.1 s 29.26 h 238.1 m 348.6% 3
243.9 d /27.9% 24.1% I18.8% 4
55.6 m IS13.76 h 2
0.6% /2.45 m 103.94 h 546.5 h I23.5 s 10
95 s 110.2 s 35.7 s 31.4 s 3
1.47 s (52.63 s 9
Decay Mode
IT 99.75%,0-0.25%
P-,fi-P-z,£££
IT< 1%
£p
££E£££
E 62.9%, / J - 3 7 . 1 %
IT 86%, p - 14%0
£ ,£
Z ,zz££
IT 99. 97%,0-0.03%
0-0-
0-0-, 0-n?
PART 1-1
IsotopeZ El A
30 Zn 8031 Ga 62
6364656667686970
7172737474m757677787980818283
32 Ge 616465666768697071727373m747575m
767777m787979m8081828384
33 As 666768697071727374757677787980
T l / 2 orAbundance
116.12 ms 2632.4 s 5
2.630 m 1115 2 m 29.49 h 7
3.261 d /68 1 m 360.1% 2
21.15 m 5
39.9% 214.10 h ;4.87 h 38.1 m I9.5 s 102.10 m 332.6 s 613.2 s 25.09 s 53.00 s 91.66 s 91.23 s )0.60 s0.31 s
40 ms 1563.7 s 2530.9 s 72.26 h 518 7 m 5271 d
39.05 h 1020.5% 511.8 d 427.4% 67.8% 2
0.499 s 1136.5% 7
82.78 m 447.7 s ?
7.8% 211.30 h /52.9 s 6
88 m 119.1 s 3
39.0 s 1029.5 s 4
7.6 s4.6 s 41.9 s 41.2 s 3
95.8 ms 442.5 s 122.530 m 17
15.2 m 252.6 m 3
62 h26.0 h 180.30 d 617.78 d 3
100%26.32 h 738.83 h 590.7 m 2
9.01 B IS15.2 s 2
Decay Mode
0-£££££
J
0-99.59%,£ 0.41%
0~0~0-IT, 0-?fi-0~0-0-0- , 0-n 0.098%0- , 0-n 0.84%0- , 0-n 12%
0-,' 0-n£, £p££, £p0.013%£
£
£
IT
0~IT 99.97%,/?- 0.03%
0-0-79%, IT 21%0~0-0-96%, IT 4%0"0", 0-
0-
£££
£f££
£65.8%, 0-34.2%
0-
0-0-0-
IsotopeZ El A
33 As 818282838484m858687
34 Se 68697071727373m7475767777m787979m808181m82
8383m84858687888991
35 Br 7072737474m757676m7777m78
7979m8080m818282m838484m85868788899091
T l / 2 orA b u n d a n c e
33 s 219 s14 s13 s
5.5 s 30.65 s
2.028 s 120.9 s 20.75 s 6
1.6 m27.4 s 241.1 m4.74 m 58.40 d 87.15 h 839.8 m 13
0.9% 1119.770 d 10
9.0% 27.6% 2
17.45 s 1023.6% 6
£65000 y3.91 m 549.7% 718.5 m 1
57.25 m 91.4>1020 y
9.2% 522.5 m 270.4 s 33.2 m 2
31.7 s 915.3 s 9
5.55 s 201.53 s 60.41 s 40.27 s 5
80 ms78.6 s 24
3 . 4 m 32 5 . 3 m 3
4 1 . 5 IB 1597 m 2
16.2 h 21.31 s 2
57.036 h 64.28 m 106.46 m 4
50.69% 54.864 s 3517.68 m 24.42 h 149.31% 535.30 h 36.13 m 82.39 h 231.80 m 8
6.0 m 22.90 m 655.0 s 8
55.69 s 1316.3 s 3
4.53 s (01.71 s 140.541 s 5
Decay Mode
0-
t „0-, 0-n0-, 0-n 0.1%0-0-, 0-n 23%0-, 0-n«4%0-.0-n£t , £p0.077.££££IT 73%, £ 27%
£
IT
0-IT
0-IT, 0-0.07%
20-
0-fi-ll-
0-0- , 0-n 0.16%0- , 0-n 0.8%0- , 0-n 5%0- , 0-na:21%£€z£
Z£
£IT 99.4%, £ 0.6%£
IT££99.99%,0-sO.Ol%
IT0-91.7%, £8 .3%IT
0-IT97.6%, 0-2.4%0-0-0-0-0-0- , 0-n 2.3%0- , 0-n 6%0- , 0-n 13%0- , 0-n 23%0- , 0-n 9%
10 TULI
TABLE I (cont.)
IsotopeZ El A
35 Br 9294
36 Kr 71727374757677787979m808181m828383m848585m8687888990919293949597?
37 Rb 747576777878m79808181m8282m838484m858686m
87
88899090m919293949596979899
100
T l / 2 orAbundance
0.365 s 7
0.1 s17.2 s 3
27.0 s 1211.50 m 11
4.3 m )14.8 h /74.4 m 60.35% 2
35.04 h 1050 s 32.25% 2
2.1«105 y 213.3 s11.67. /u.5% /1.83 h 257.0% 3
10.72 y 24.480 h 8
17.3% 276.3 m 52.84 h 23.07 B 932.32 s 98.57 s 51.85 s 1
1.289 s 120.20 s /0.78 s 3<0.1 s65 ms
17.2 s 839.1 s 63.70 B 1517.66 a 85.74 m 622.9 m 5
34 s 44.58 h /
32 m1.25 m 36.2 h 586.2 d 1
32.87 d //20.49 B 1772.165% 1318.66 d 21.017 m 3
4.80-1010 y 1327.835% 13
17.8 i I15.2 m 1153 s 3258 s 558.4 s 44.50 s 25.85 s
2.702 s 5384 ms 60.199 s 3
171.8 ms 160.114 s 5
59 ms50 ms
I
0-0-£££ ,££££
£IT
£IT
IT
0-0-
0-0-
0~0-B~0-
£££££
)ecay Mode
0-n 21%0-n > 0%
£P 0.687.
79%, IT 21%
/J-n 0.037./3-n 1.955/S-n5.7%0-n
£90%, IT 8%££££ ,£
£f
IT
£ 96%, 0- 4%IT
($- £0.005%IT>99.7%,/J-<0.3%
2-0-ft~0-0-
2-0~0~0~0-0-
95.7%, IT4.355
/3-n 0.012%/J-n 1.3%/J-n 10.4%/3-n 9.1%/J-n 13%/J-n 24.6%/J-n 15.9%/J-n0-n
IsotopeZ El A
37 Rb 102?38 Sr 77
78798081828383m848585m868787m888990919293949596979899
100101102
39 Y 80818283838484m8585m8686m8787m
888989m9090m9191m929393m94959696m96m9797m9898m99
100100m101
Tl/2 orAbundance
90 ms 209.0 s 10
30.6? a 232.25 B 10106.3 m IS
22.2 m25.6 d32.4 h 2
4.95 s 120.56% /
64.84 d 367.66 a 7
9.86% 17.00% 1
2.81 h 182.58% /50.55 d 928.6 y 39.52 h 62.71 h 17.6 n 2
75.1 s 725.1 s 21.06 s 40.42 s 30.65 s 30.29 s0.2 s
121 ms 6355 ms 5033.8 s 6
72 s9.5 s
7.06 m 82.85 B 240 m /
4.6 s 22.68 h 5
4.86 h 1314.74 h 2
48 m /80.3 h 312.9 h 4
106.64 d 8100%
16.06 s 464.1 h /3.19 h 158.51 d 649.71 m 43.54 h /10.1 h 20.82 s18.7 m 110.3 m 26.2 s 29.6 s 22.3 B /3.5 s 21.23 s 20.64 s 32.0 s 21.5 s
0.94 s0.5 s
0.50 s 5
Decay Mode
0-t, £p<0.25%tceecfIT
£IT 87.3%, £ 12.7%
IT 99.7%, £0 .3%
fi-0-0-0-0-0-fr0-B-, 0-n 0.27%B-, /S-nO.8%P-. /3-n
2-0-0-££f£££E£E£IT99.31%, E 0 . 7 %£IT 98.437.,r l . 5 7 %£
IT0-IT, 0-0.002%0-IT0-0-IT0-0-0-0-0-fi-'
fi-ll- , 0-n 1%0-0-0-
w COt
.5-
;c *o
• OT ™-?<o^-^<«*.iA-.r• r>«-« - ' •
t- m <o t - oo O - c-oo O) O) o—-c\j N n ^f m co i-oo o> o w n e*5 •<* \n <iJ) O) 0- — —
->— 43 O
HOS
yr -^
O )
o in
- A
Jt^cjcj^ -^^ i -- . ixo^.
O) O
OOOOOOOCOCOUCOfOCo en .*»• co ro * - o co co i o> ui 4
3
£ ; . - c
9 3
ro.f* »— c
SI
CO CO
>
S2
W
o3
-3 11 - 3 O I -3 - 3 ^ , (o -3o co • co CJICJ* r j co
CO - 3 ^en as c»
H
r
CD f\jfow(\Jr -ooooo >r
0 0 < o
t o o o o u . ^ ^
i i Icooo
en z?<a ^ro
i CO K— CD CO •—' - CO\ CO " 00 CO ' 00 ' ^
i
ro "^
3
_ - 3CO • CO
cooooo
s ^9
3 =
CJ>1%,
Co3 3 3Co
01 •» " ' U) l
PART 1-1 13
I s o t o p eZ El A
48 Cd 9899
100101102103104105106107108109110111111m112113
113m
114115115m116117117m118119119m120121121m122124126128
49 In 100102103104105105m106106m107107m108108109109m109m110110111Him112112m113113m114114m115
115m116
116m
T l / 2 o rAbundance
£zo s16 s
1.1 ID 31.2 m 25.5 u 57.3 a 1
57.7 m 1055.5 m 41.25% 3
6.50 h 20.89% 1
462.9 d 2012.49% 912.80% 648.6 m 324.13% 11
9.3-10 1 5 y (912.22% 6
13.7 y
28.73% 2153.46 h 1044.6 d 37.49% 92.49 h 43.36 h 550.3 m 22.69 m 22.20 m 2
50.80 s 2113.5 s 3
8 s5.5 s 10.9 s 2
0.506 s 150.94 s 5
23 s 465 s 71.7 m 24.9 m 343 s
6.2 a I5.2 m 132.4 m 350.4 s 639.6 ni 7
58.0 m 124.2 h (1.34 m 70.21 s (69.1 m 54.9 h /2.83 d 17.7 n 214.4 m 220.9 m 2
4.3% 21.658 h 171.9 s 149.51 d 1
4.41-101* y 2595.7% 2
4.486 h 414.10 s 3
54.15 tn 6
Decay Mode
f, fp?f, cp££££££
£
£
IT
P-P- 99.86%,IT 0.14%
0-0-
0-0-0-P~0-0-P-P-P-0-P-P-£. £p£££€IT£££
IT£
£
ITIT£££IT£56%, 0-44%IT
IT0-99.5%, £ 0 . 5 %IT95 .7%, £ 4 . 3 %0-1T957.,0-5Z
£<0.06%0-
IsotopeZ El A
49 In 116m117117m
118118m118m119119m120120121121m122122123123m124124m125125m126126m127127m128129129m130130131132
50 Sn 103104105106107108109110111112113113m114115116117117m118119119m120121121m
122123123m124125125m126127127m128128m
Tl/2 orAbundance
2.18 s 443.8 m 7116.5 m 7
5.0 s 34.45 m 58.5 s 32.4 m 118.0 m 3
44.4 s 103.08 s 823.1 s 63.88 m 1010.0 s 51.5 s 3
5.98 s 647.8 s 53.17 s 52.4 s 42.33 s 412.2 s 1
1.45 s 221.5 s 21.15 s 53.76 s 30.9 s 1
0.59 s 21.26 s 20.51 s0.53 s 50.27 s 20.22 s7 s 3
31 s2.10 m 152.90 m 510.30 m 818.0 m 2
4.11 h (035.3 m 80.97% I
115.09 d 421.4 m 40.65% 10.36% 1
14.53% 117.68% 7
13.61 d 424.22% 118.58% 4
293.0 d 1332.59% 1027.06 h 4
55 y 5
4.63% 3129.2 d 440.08 m 75.79% 59.64 d 39.52 m 5
sl.0-105 y2.10 h 44.13 m 359.1 m S6.5 s 5
Decay Mode
IT0-£-52.9%,IT 47.1%0-0-IT98.5%, j8- 1.5?0-£-97.5%, IT 2.570-0-0-£-98.8%, IT 1.2?0-0-0-0-0-P-0-0-0-0-0-P-, 0-n0-0-0-P-0-0-0-
0-/i-n
p-nfi-nP-n0-n
f, ^P
£ , £p££££££
tIT 91.1%, £8.9%
IT
IT
0-IT77.655,£-22.4%
P-0-
P-0-P-0-P-0-1T
14 TULI
TABLE I (cont.)
IsotopeZ El A
50 Sn 129129m130130m131131m132133134
51 Sb 108109110111112113114115116116m117118118m119120120121122
122m123124124m124m125126126m126m127128128m129129130130m131132132133134134135136
52 Te 106107108109110111112113114115115m116117118119
Tl /2 orAbundance
2.16 n 46.7 n 4
3.72 m 111.7 m 161 s 339 s
40 s 11.47 s1.04 s 27.0 s 517.0 s 723.0 s 475 s /
51.4 s 106.67 m 73.49 m 332.1 m 315.8 m 860.3 n 62.80 h 1
3.6 m5.00 h 138.1 h 215.89 m 45.76 d 257.37. S
2.70 d /
4.2 m 242.7% 9
60.20 d 393 s 5
20.2 n 22.73 y 312.4 d 119.0 • 3=11 s
3.85 d 59.01 h 310.4 m 24.40 h (17.7 m38.4 m6.3 n 223 n 24.1 m3.07 a2.5 m
0.85 s 1010.43 s 14
1.71 s0.82 s 20.06 ms
3.6 ms +6-42.1 s 14.6 s 318.6 s 819.3 s 42.0 m 21.7 m 2
15.2 m 75.8 m 26.7 a 4
2.49 h 462 B 2
6.00 d 216.05 h 5
Decay Mode
P~B-, IT0.0002%P~P-p-P-P-P-, P-DP-, /8-nl7%£, £p££
£££tz£££££££
P- 97.62%,£ 2.38%IT
P-IT 75%, ,3-25%ITP-P-/J-86%, IT 14%ITP-P-0-96.4%, IT3.6%P-P-fi-P-P-fi-P-P-P-S-, /?-n0.1%fi-, /?-n20%/?-, /3-n32%aa 70%, £ 30%a 68%, £ 32%, £p£ 96%, £p, a4%£, a£, £ p , a££c£tCttt
IsotopeZ El A
52 Te 119m120121121m122123
123m124125125m126127127m
128129129m
130
131131m
132133133m134135136137138
53 I 110
111112113114115116117118118m119120120m121122123124125126127128129130130m131132132m133133m134134m135136136m137
Tl/2 orAbundance
4.69 d 40.096% 2
i a .78 d 35154 d 72.60% ;
1.3-101 3 y0.908% 3119.7 d /4.816% 87.14% f58 d 1
18.95% /9.35 h 7109 d 2
>8.»102 4 y31.69% 269.6 a 233.6 d 1
2 . 5 M 0 2 1 y 2733.80% 225.0 m /30 h 2
78.2 h 812.45 a 2855.4 m 441.8 n 819.2 s18 s
3.5 s 51.4 s 4
0.65 s 2
7.5 s3.42 s 115.9 s 52.1 s 228 s
2.91 s 152.3 m 114.3 B8.5 m 519.1 m 481.0 m 653 m 4
2.12 h 13.62 m 613.2 h 14.18 d 2
60.14 d 1113.02 d 7
100%24.99 m 2
1.57«10' y i12.36 h 19.0 a (8.04 d /2.30 h 383.6 m 1720.8 h 1
9 s52.6 n 43.69 m 76.61 h 1
84 s 145 s /
24.5 s 2
Decay Mode
£
f
IT 88.6%, £ 11.4%
£
IT
IT
P-IT97.6%, /S-2.4%2/8-
P-IT64%, 0-36%2/8-
P-/3-77.8%,IT22.2%P-P-0-83%, IT 17%P-P-P-, /J-nO.7%P-, 0-nZZP-, /8-n 6%£ 83%, a 17%, rp,£a£99.9%, a 0.1%£, £p, fa , a£ , £Cf, a£££
£E
£. IT£££C£££
£56 .3%, /J-43.77.
/J- 93.1%, £6 .9%P-P-IT83%, /?- 17%P-P-IT86%, 0- 14%fi-llfi-ll 97.7%, /?-2.3%fi-fi-P-0-, /8-n 6.4%
PART 1-1 15
IsotopeZ El A
53 I
Tl /2 orAbundance
54 Xe
138139140141142110111111112113114115116117118119120121122123124125125m126127127m128129129m130131131m132133133m134134m135135m136137138139140141142143143144145
55 Cs 114
115116116117118
119119120120121121m122122123
1
6.41 s 52.30 s 50.86 s 40.43 s 20.2 s0.2 s0.7 s0.9 s 22.8 s 22.8 s 210.0 s 4
18 s 456 s 261 s 2
4 m5.840 m
40.1 B 220.1 h 12.08 h 20.10% 116.9 h 257 s 1
0.09% 136.4 d I69.2 s 91.91% 326.4% 6
8.89 d 24.1% 121.2% 411.9 d I26.9% 5
5.245 d 62.188 d 8
10.4% 2290 ms 179.09 h I15.29 m 3
8.9% I3.818 n 1314.08 m 8
39.6813.601.73 s1.22 s 2
s 3s 2
0.300.961.15 s 200.9 s 30.57 s 2
Decay Mode
0- , /3-n 57./3-, /3-n 10%0- , /J-n 14%P-, /3-n 21.2%
£, a£
£99.16%, a 0.84%£, £p, ta, a
£, £pO.3%££ ,£
tpO.003%
f£££
£
IT
£
IT
IT
IT
ITfi-ll, p - 0.004%
0- , 0-n 0.044%
P-,fi-n£, £p7%, EaO.16%,a 0.02%1.4
3.810.71
6.516.4
37.72864
60.2136121
4.521.05.87
sssss
ssssssmsm
8IS8
12
101
15
275
£ ,£ ,£ ,£
£ ,
£pO.3%£p, £O£p, £0
£PO.O4%,£a0".0024%£ ,
£ ,££
n£££
£<X?
£p, ta
\ £
IsotopeZ El A
55 Cs 123m124124m125126127128129130131132133134134m135135m136136137138138m139140141142143144144?145146147148
56 Ba 117119120121122123124125125126127128129129m130131131m132133133m
Tl/2 orAbundance
1.60 s30.8 s6.3 s45 m i
1.64 m6.25 h3.62 B32.06 h
29.2 B9.69 d
6.475 d100%
2.062 y2.91 h3»106 i
53 m J13.16 d
19 s ;
(55
2f
21026
;10
51
I7
' 37
30.17 y32.2 B
2.90 m9.27 m63.7 s24.94 s
1.8 s1.78 s1.02 s
<1 s0.59 s
0.343 s0.22 s170 ms1.9 s
5.35 s32 s
29.7 s2.0 m
2.7 m11.9 m3.5 B
8 m100 m
12.7 m2.43 d
2.23 h2.17 h0.106%11.8 d14.6 m0.101%10.74 y38.9 h
110536
13
1717
230
15
4104
245114222251
134135135m136136m137137m138139140141142143144
2.417% 276.592% 1828.7 h 2
7.854% 390.306 s11.23% 4
2.5513 m 771.70% 7
84.63 m 3412.746 d 1018.27 a 710.6 n 214.5 s 511.4 s 5
Decay Mode
IT£ITf££££
£ 98.4%, p- 1.6%
£98%, 0-2%0 - , £0.0003%IT
IT
0-
IT81%, 0- 19%
0-n 0.029%/J-n 0.28%0-n 1.7%0-n 3%
/3-n 12%0-n 14%0-nI
fi-£, £P£, £p£, £p0.02%££££E£££££
CIT
IT 99.99%,£0 .01%
IT
IT
IT
i
16 TULI
TABLE I (cont.)
IsotopeZ El A
56 Ba 145146147148
57 La 123124125126127127m128129129m130131132132m133134135136137138 1
139140141142143144145146146m147148149
58 Ce 124125126127128129130131131132133133134135135m136137137m
138139139m140141142
143144145146147
Tl/2 orA b u n d a n c e
4.0 s2.20 s 30.72 s 7
0.607 s 2517 s 329 s 376 s 61.0 m 33.8 m 55.0 m ?5.0 ID 311.6 m 20.56 s 58.7 m 159 m 2
4.8 h 224.3 m 5
3.912 h 86.45 in 16
19.5 h9.87 m 3
6»104 v 2.28«10'^ y 12
0.09% 199.91% ;
40.272 h 73.92 h 391.1 m 5
14.23 m 1440.9 s 424.8 s 206.27 s 1010.0 s 14.4 s 51.05 s /1.2 s 46 s 29 s
50 s 632 s 4
6 m3.5 n 525 m 210 m 15 m 1
3.5 h5.40 h 5
97 a75.9 h 917.6 h20 s
0.19% 19.0 h 3
34.4 h 3
0.25% 1137.66 d 13
56.4 s 588.48% 10
32.501 d 5>5-1016 y11.08% 1033.0 h 2284.4 d
2.98 m 1513.52 m (356.4 s 12
Decay Mode
0-0-0-, 0-n/?-, 0-n£££££
££ITtz£IT 76%, c 24%£
££
££
£ 66.7%, 0-33.3%
0-t>-0-0-0-0-0-0-0-, 0-n0-0-f
£, £p£££
£££££ff£
IT
£IT 99.22%,£0.78%
£
IT
0-
0-0-0-0-0-
IsotopeZ El A
58 Ce 148149150151
59 Pr 121129130132133134134m135136137138138m139140141142
142m143144144m
145146147148148m149150151152
60 Nd 129130132133134135135m136137137m138139139m140141141m
142143144
145
146147148149150
151152154
T l / 2 o rA b u n d a n c e
56 s 15.2 s 34.0 s 61.02 s 61.4 s 824 s 528 s
1.6 m 36.5 m 317 m 211 a25 m
1 3 . 1 m (1.28 h 21.45 m 52 . 1 h 1
4.41 h 43.39 m 1
100%19.12 h 4
14.6 m 513.58 d 317.28 m 57.2 m 2
5.98 h 224.15 m 18
13.6 m 52.27 m 42.0 m t
2.26 m 76.19 s )6
4.0 s 73.2 s
5.9 s 628 s1.8 oi1.2 m
8.5 m 151 2 ID
=5.5 m50.65 m 3338.5 m 151.60 s 155.04 h S29.7 m 55.5 h 23.37 d 22.49 h 362.4 s 9
27.13% 1012.18% 5
2.1-10'= y 423.80% 10>6«10'6 y8.30% 517.19% 8
10.98 d 15.76% 3
1.725 h 7> M 0 1 8 y5.64% 312.44 ID 711.4 m 240 s 10
Decay Mode
0-0-0-0-£, £pc£££f£££
£££
£
0-99.98%,£ 0.02%IT0-0-IT99.96%,0-0.04%0-0-0-0-0-0-0-0-0-£, £p££££
££££IT£££ 88%, IT 12%££IT 99.97%,£ 0 . 0 3 %
a
a
0-
0-20-
0-0-0-
PART 1-1 17
IsotopeZ El A
61 Pm 132133134135136137138139140140m141142143144145146147148148m149150151152152m152m153154154155
62 Sm 133134135136137138139139m140141141m
142143143JD
144145146147
148
149
150151152153154155156157158
63 Eu 138138139140
Tl /2 orAbundance
4 s12 s
24 s 20.8 m107 s 62 . 4 is /
3.24 m 54.15 m 59.2 s 2
5.95 m 520.90 B 540.5 s 5265 d 7363 d 1417.7 y 45.53 y 5
2.6234 y 25.370 d 9
41.29 d 1153.08 h 52.68 h 228.40 h 44.1 m 1
7.52 m 815 B 1
5.4 B 21.7 B 22.7 n /48 s 432.0 s12 s 310 s42 s
44 s 83.0 B 3
2.57 B 109.5 s 10
14.82 m 1010.2 m 222.6 B 2
72.49 m 58.83 m 1
66 s 2
3.1% 1340 d 3
10.3-10' y 51 .06-10" y 2
15.0% 27-101* y 3
11.3% />2-101 5 y13.8% 17.4% /90 y 626.7% 2
46.7 h 122.7% 2
22.1 m 29.4 h 28.0 m 55.51 m 9
35 s 61.5 s 422 s 3
20 s +15-1
Decay Mode
£
£
£
£
££
f
£££
£
£
£
£
£, aw£66.1%, 0-33.9%P~0-0-95.4%, IT4.6%0-0-0-0-0-0- , IT0-0-0-Z , £p££, £p£
££
£
IT 9 3 . 7 % , £ 6 . 3 %££
£99.69%,ITO.31%££IT 99.76%,£0.24%
zaa
a
a ?
0-
0-
0-0-P-0-£
£
C
Z
IsotopeZ El A
63 Eu 140141141m142142m143144145146147148149150150151152
152m152m153154
154m155156157158159160
64 Gd 142143143m144145145m146147148149150151152
153154155156157158159160161162163
65 Tb 144145146146m147147148148m149149m150150151
T l / 2 o rAbundance
1.3 s 240.0 s 73.3 s 32.4 s 21.22 m 22.63 m 510.2 s 15.93 d 44.59 d 3
24 d 154.5 d 593.1 d 4
12.62 h 1035.8 y 1047.8% 5
13.33 y 4
9.32 h 196 B 1
52.2% 58.8 y 1
46.0 B 34.96 y 115.19 d 615.15 h 445.9 m 21 8 . 1 m ;44 s 41.5 B 339 s 21.83 B4 . 5 m 1
23.9 m 185 s 3
48.27 d ro38.1 h r74.6 y 30
9.4 d J1.79«106 y 8
120 d 201 .08-10 1 4 y 8
0.20% 1241.6 d 2
2.18% 314.80% 520.47% 415.65% 3
24.84% 1218.56 h 821.86% 43.66 m 58.4 m 268 s 3
5 s30 s8 s 4
23 s 21.65 h 101.83 m 660 m 1
2.20 m 54.13 h 24.16 B 43.27 h 10
5.8 m 217.6 h )
Decay Mode
££f67%, IT 33%£££££££, aw£, aw£0-89%, £ 11%£
£72.08%,0-27.92%0- 72%, £ 28%IT
0-99.98%,£0.02%IT0-0-0-0"0-0-£££, IT?£
£
IT 95 .3%, £ 4 . 7 %££a£, awaE , awa
£
0-0-0-0-f££
£
££
£
£
£82.8%, a 17.2%£, a 0.022%£ a—0 05%
£, a 0.01%
18 TULI
TABLE I (cont.)
IsotopeZ El A
65 Tb 151m152152m153154154m154m155156156m156m157158158m159160161162163164165
66 Dy 145146147147m148149150151152153154155156
157158159160161162163164165165m
166167168
67 Ho 146147148148m149150150151151152152153153m154154155156156m
Tl/2 orAbundance
50 s17.5 h 34.3 n 22.34 d 121.4 h 59.0 h 5
22.6 h 65.32 d 65.34 d 95.0 h 1
24.4 h 10150 y 30150 y 3010.5 s 2
100%72.3 d 26.90 d 2
7.76 m 1019.5 a 33.0 n 1
2.11 a 1018 s
29 s 380 s58 s
3.1 m 14.23 n 187.17 m 216.9 m 52.38 h 26.4 h /
3«106 y10.0 h 3
M.O-IO 1 8 y0.06% 18.1 h /0.10% 1
144.4 d 22.34% 518.9% I25.5% 224.9% 228.2% 2
2.334 h S1.258 m 6
81.6 h 16.2 m
8.5 m 53.9 s 8
9
2.2 s 119 s 1
21.4 s 1872 s >0
24 s35.6 s 447 s 2
2.35 m 1152.3 s 52 .0 m 19.3 m 511.8 m 53.2 m 148 m ;
2 it55.6 n 6
Decay Mode
IT£IT78.9%, £ 21.1%c€£78.2%, IT 21.8%r 9 8 . 2 % , IT 1.8%££IT, £, 0-WIT££82%, 0 - 18%IT
P-0-P~P-0-P~t££IT, £, £p£££ 64%,a 36%£ 9 4 . 4 % , a 5 . 6 %£99.9%, a 0 . 1 %£99.99%, a 0 . 0 1 %a£
£
£
P-IT97.76%,/S-2.24%P-P-P-£
£, £p££
£££
£ 90%, a 10%£ 80%, a 20%£ 88%, a 12%£89.5%, a 10.5%£99.95%, a0.05%£99.82%, a 0.18%£, aO.017%£, a<0.002%£, a£I T , £
IsotopeZ El A
67 Ho 156?157158158m158m159159m160160m160m161161m162162m163163m164164m165166166m167168169170170
68 Er 147148149150151152153154155
156157158159160161162163164165166167167m168169170171172173
69 Tm 147148150152153154154155156156157158
Tl/2 orAbundance
7.4 m12.6 m 211.3 oi 4
21 .3 m 2327 m 233 m 1
8.30 s 835.6 n 35.02 h 5
<2 B2.48 h 56.73 s 10
15 m 167 m />10 y
1.09 s 329 in 1
37.5 m t/5-5100%
26.80 h 21.20-103 y 18
3.1 h ;3.0 m /4.7 m (2.8 n43 s
2.5 s4.5 s 4
9 s 218.5 s 723 s 210.3 s37.1 s
3.75 m 125.3 m 3
20 n25 m 3
2.25 h 736 m
28.59 h 93.21 h 30.14% 1
75.0 m 41.61% (
10.36 h 433.6% 2
22.95% 132.28 s 326.8% 29.40 d 214.9% 1
7.52 h 349.3 h 51.4 n 10.5 s
0.7 s 23.5 s 6
5 s1.59 s 88.3 s3.4 s25 s80 s 319 s 3
3.5 it 24.02 m 10
Decay Mode
££££IT 65%, £35%tIT£IT 65%, £35%otITtIT 63%, £37%tIT£58%, /?- 42%IT
P-P-P-P~
frP~P-C, £p£r , £p££a 90%, £ 10%a 53%, £47%£ , a O . 5 %£<99.98%,a.2 0.02%££££££
£
f
IT
P-
P-P-P~p£££a295%, ££5%£, o;a , £a, t£, aa£, aw£
PART 1-1 19
IsotopeZ El A
69 Tm 159160161162162m163164164m165166167168169170
171172173174175176
70 Yb 153154155156157158159160161162163164165166167168169169m170171172173174175176176m177177m178179
71 Lu 151154155156156157158159160161162162m162m163164164?
Tl/2 orAbundance
9 m9.2 a 438 g 4
22.0 m 724.3 s 171.81 h 62.0 m 15.1 n /
30.06 h 117.70 h 39.24 d 293.1 d /
100%128.6 d 3
1.92 y 163.6 h 28.24 h 85.4 g 115.2 is 51.9 m /4.0 s 5
0.42 s 21.65 s 15
24 s /38.6 s 101.38 m 14
12 s4.8 m 24.2 g 2
18.87 n 1911.05 g 2575.8 m (7
9.9 n56.7 h 117.5 m 20.13% 1
32.022 d 846 s 2
3.05% 514.3% 221.9% 3
16.12% (831.8% 44.19 d 112.77. )11.4 s 51.9 h /
6.41 s 274 m 38 n
0.09 s1.0 s
0.07 s 2=0.5 s0.23 s 35.5 s 310.4 s /
12 s35.5 s 872 s 6
1.37 m 2=1.5 ms l . 9 •4.1 in3.17 n
2 in
Decay Mode
E
rttIT 90%, £ 10%££IT 80%, t 20%tc£E, 0 -?
/J-99.85%,c 0.157.fi-/»-0-0-/»-/»-£
aa s 90%, t£, a 21%£99.5%, aO.5%f, a 0.003%£, a£
£££££££
£
IT
fi-
llfi-llfi~fi-PE
a, Ea, £ac94%, a6%£>98.5%, a<1.5%£ , G
£cITIT££
IsotopeZ El A
71 Lu 165166166m166m167168168m169169m170170m171171m172172m173174174m
175176
176m177177m178178m179180181182183
72 Hf 154155156157158159160161162163164166167168169170171172173174
175176177177m177m178178m178m179179m179m180180m181
Tl/2 orAbundance
12 m 12.8 a
1.41 m (02.12 m 1051.5 m 10
5.5 a6.7 m 4
34.06 h 5160 s (02.00 d 30.67 s 108.24 d 379 s 2
6.70 d 33.7 g 51.37 y 13.31 y 5142 d 2
97.41% 23.60*10'° y 16
2.59% 23.68 h 16.71 d 1160.9 d 328.4 m 2
23 n4.59 h 65.7 g ;3.5 m 32.0 m58 s2 s
0.9 s25 ms 4110 ms 62.9 s 25.6 s=12 s17 s 2
37.6 s 840 s
2 . 8 m Z6.77 m 302.05 m 5
25.95 in 23.24 m 4
16.01 h 1312.1 h 41.87 y 323.6 h
2.0»10 1 5 y 40.162% 2
70 d 25.206% 418.606% 31.08 s 651.4 n 527.297% 3
4.0 s 231 y /
13.629% 518.68 s 625.1 d
35.100% 65.5 h /
42.39 d 6
Decay Mode
£££58%, IT 42%£>80%, IT<20%££
£, IT1?£
IT£
ITEIT£
IT£CIT 99.35%,f0.65%
fi-
fi-fi-/S-79%, IT 21%fi-fi-fi-fi-fi-0-fi-£
£
aa 91%, £9%t 54%, a 46%t, at , aac£
£
£££EE
£E
a
£
ITIT
ITIT
ITIT
ITfi-
o
lOlO
m ***
O
.OO
3%, a
O OO-O>
£5?3O O
O O
. 0 a
0.3%
98%
,98
%,
VI - .~ I
N«"S a'
s
CJ •* or- aCO lO ,CTJ
3 O UJ w ^ w O i
Co
- T- >~ ^ O ^f "t
= x : e T 3 E B o •
* ^ f OJ OO ^ ^ OJ • ^ " r . --.CO - ^ " " S ,; in in
,o r - • -- . CO
O) CO —"
7jf,r-ir>Tr I-JQ^J •. . ^ ^ c .
^oO^.no^S
CVI CM CO •**• iCO OO CO CO I
COCOCDCOCOCOCOCDOOCOCOCOOOOOOOC0030POO--J--^-^--J^J^J^J--J-J^JC7JCnO)0) <O<O<0<O<O<£><£><O<J3<OCX>CDaoCOro M M • — H * 3CDOQ-JO)05U>4^COfOH-*OCOCO^JC7)CJ14i'CJrO^-0<OCO-^3CT) CT)Cn.fkCOfOfO*->—•OOCOCOCO--I
^ ^ ( V j ^ ^ ^ ^ U , C O Co _ — 4
73H
jrU^woo^^"°^^°°-^- •1 o TWm"?J "v| CO
3 a, — " ^ ^
- IV IA (o" )) II <o
C O ^
ft Q Q Q O O "tests, — Ts> — t) i 3 ) 3i
o • uoo
» o
b o
22 TULI
TABLE I (cont.)
IsotopeZ El A
79 Au 193m
194195195m196196m196m197197m198198m199200200m201202203204
80 Hs 177178179180181
182183184185185m186187187188
189189190191191m192193193m194195195m196197197m198199199m200201202203204205206207
31 Tl 184185m186186m187187m188
Tl/2 orAbundance
3.9 s 3
39.5 h 5186.1 d30.5 s 2
6.183 d 108.1 s 29.7 h 1
100%7.8 s 1
2.696 d 22.30 d 43.139 d 748.4 m 318.7 h 526 m 128 s 253 s 240 s 30.17 s
0.47 s 141.09 s2.9 s 33.6 s 3
11.2 s 108.8 s 530.6 s 350 s 220 s 2
1.38 n 102.4 m 31.9 m 3
3.25 a 15
7.6 m8.6 m
20.0 m 549 m 10
50.8 m 154.85 h 203.80 h 1511.8 h 2520 y9.5 h
40.0 h0.14% 1064.1 h 123.8 h 110.02% 716.84% 1142.6 m 223.13% 1113.22% 1129.80% 1446.60 d 2
6.85% 55.2 m /
8.15 m 102.9 m 211 s ;1.8 s 228 s4 s50 s
15.60 s 1271 s 10
Decay Mode
IT=99.97%,£=0.03%££IT£92.5%, ^-7.5%ITIT
ITP~IT
0—P- 82%, IT 18%0-0~0-CC, £
a=84%, £=16%a 53%, £47%, cpw£ , ft£>87%, a<13%,tpw , zan£91%, a 9%£ 88%, a 12%, EDW£ 98.75%,a 1.25%£595%, a25%£, IT, a£, aO.02%£, a>0.0001%£, a>0.0002%£>99.99%,a<0.01%£zz£££££92%, IT 8%££IT 54.2%, £45.8%
£IT 93%, £ 7%
IT
0-
P-P-0-£ 98%,a 2%IT, a£, awIT£IT, £, a£
IsotopeZ El A
81 Tl 188m189189m190190191m192192193193m194194m195195m196196m197197m198198m199200201202203204
205206206m207207m208209210
82 Pb 183184185186187187188189190191191m192193194195195m196197197m198199199m200201201m202202m203203m203m204
Tl/2 orAbundance
71 s 12 . 3 m1.4 m
2.6 m 33.7 m 3
5.22 m (69.6 m 410.8 m 221.6 m 82.11 n 1533.0 m 532.8 m 21.16 h 53.6 s 41.84 h 31.41 h 22.84 h 40.54 s 15.3 h 51.87 h 37.42 h 826.1 h 173.1 h 212.23 d 229.524% 93.78 y 2
70.476% 94.20 m 23.76 m 44.77 n 21.33 s 1!3.053 m2.20 m 71.30 m 3
0.6 s4.1 s 37.9 s (618.3 s 315.2 s 3
24.5 s 1551 s
1.2 m ;1.33 m 82.2 m
3.5 m /5.8 m 2
10 m15 m
15.8 m 237 a 3
8 m43 m
2.4 h 190 m 1012.2 m 321 .5 h 49.33 h61 s 2
5.3-10+ y3.53 h51.88 h0.48 s 26.3 s 2
21.4-1017 y1.4% 1
Decay Mode
£E
z££££££IT 75%, £25%£££IT££95.5%, IT4.5%£
IT££54%, IT 46%£££f
JS- 97.45%,£ 2.55%
0-ITP-IT0-0-0-, /J-n 0.007%aaa£, a=2.4%£ 98%,a 2%a, ££78%, a 227.£>99%, a=0.4%f99.1%, a 0.9%£99.99%, a 0.01%££99.99%, a 0.01%££££c, a<0.0001%£c81%, IT 19%, a££IT 90%, £££IT£IT90.5%, £ 9 . 5 %£
ITIT
PART 1-1 23
IsotopeZ El A
82 Pb 204m205206207207m208209210211212213214
QO D; toojO Dl 1OO
189190191191m192193193m194195195m196197197m
198198m199199m200200m200m201201m202203204205206207208209210210m211
212
212m212m213
214
21584 Po 192
193193m194195195m196197197m
Tl/2 orAbundance
66.9 it1.52-10' y 7
24.1% )22.1% 10.796 s52.4% /
3.253 h 1422.3 y 236.1 i 210.64 h 110.2 m 326.8 it
s i 5 s5.4 s 513 s 1
20 s 1542 s 564 s 43.5 s 2105 s 15170 s 2090 s 54.6 m 5
9
9.5 m 10
11.85 in 187.7 s 527 it 1
24.70 m 536.4 it 531 m 2
0.40 s 5108 m 3
59.1 m 61.72 h 511.76 h 5
11.22 h 1015.31 d 46.243 d 332.2 y 9
3.68-10* y 4100%
5.013 d 53 . 0 - 1 0 6 y 1
2.14 m 2
60.55 m 6
25 m9 m
45.59 m 6
19.9 it 4
7.4 m 60.034 s 3
450 ms (500.42 s0.7 s
4.5 s 52.0 s 25.5 s 556 s 326 s 2
Decay Mode
IT£
IT
fi-ll-, aw0-0-0-0-aas: 90%, £
£, a£ 80%, a 20%a 60%, £40%£, a=25%£>99.8%, a<0.2%£>99.8%, a<0.2%£, a 4%
£=99.89%,a=0.11%
IT£E, a££IT££, IT 10%, aw££, anc£
£
£
0- , a 0.0001%aa 99.72%,0-0.28%0-64.06%,a 35.94%,0-a 0.014%a^93% 0-s7%0-0-97.84%,a 2.16%0-99.98%,a 0.02%0-aaaaaaa, ££56%, a 44%a 84%, £S16%,IT?
IsotopeZ El A
84 Po 198199199m200201201m
202203203m204205206207207m208209210211211m212212m213214215216217218
85 At 196197198198m199200200m201202202m203204205206207208209210211212212m213214215216217
218219
86 Rn 199199m200201201m202203203m204
Tl/2 orAbundance
1.76 m 35.2 it 14.2 it 111.5 m (15.3 m 28.9 m 2
44.7 m 535 it
1.2 it 23.53 h 21.66 h 28.8 d 15.80 h 22.8 s 2
2.898 y 2102 y 5
138.376 d 20.516 s 325.2 s 6
0.298 /is 345.1 s 64.2 tis 8
164.3 /is 181.780 ms 4
0.15 s<10 s
3.11 it
0.3 s 10.4 s 14.9 s1.5 s 37.0 s 143 s 24.3 s 389 s 3181 s 31.1 s
7.37 m 209.2 m 226.2 n 529.4 m 31.80 h 41.63 h 35.41 h 58.1 h 4
7.214 h 70.314 s 20.119 s 30.11 iis 2
2 fi%0.10 ms 20.30 ms 332.3 ms 4
=2 s0.9 m /0.5 s
0.29 s1.0 s 27.0 s 43.8 s 4
9.85 s 2045 s 328 s 2
1.24 m 3
Decay Mode
a 70%, f 30%£88%, a 12%£61%, a 39%£ 85%, a 15%£98.4%, a 1.6%£57%, IT40%,a=3%£98%, a 2%£ 99.89%, a0 .11%IT95.5%, £4.5%£99.34%, a 0.66%£99.96%, a0.04%£ 94.55%, o5.45%£ 99.98%, aO.02%ITa, £ 0.0018%a99.74%, £0.26%aaaaaaaa, 0 - 0.0002%aa>95%, 0-<5%a99.98%,0- 0.02%aa=96%, £=4%aa, IT?a 53%, £ 47%£65%, a 35%a, IT?a 71%, £ 29%£ 88%,a 12%IT£69%, a 31%£ 95.6%, a 4.4%£ 90%, a 10%c 9 9 . 0 4 % , a O . 9 6 %£ 91.3%, a 8 . 7 %£99.45%, a 0.55%£95.9%, o 4 . 1 %£ 99.82%, aO.18%£58.3%, a41 .7%aaaaaaa 99.99%,0-0.01%a 99.9%, 0-0.1%a 97%, 0-3%aaa=98%, £=2%ass 80%, £=20%a, £a=85%, £=15%a 66%, £ 34%aa 68%, £ 32%
— o
10 K
KO)ZCOO) OC»AO8
CO CT) O
O O O O 8 O O O O O
"~' C7) OJ
8 C w
D CO CO CO O C\J I D . - ,• * * C O - CD • C~ 0 3_,t- 3—i
cvj c*5 c-j Co^ " 'B^n^w
0)100°,-HCO
>cjcvicOjio<0(ooa>o c7>o«c\JCOTMncorHOJOJCviCviCUfMCVJCVJOJCvJCO O—<—''-<—'—<—•—I'
VCICJOJOJOJOJOJOJCJCXJCJ CJOJJCUCOOJOJJO
3^-<c\ic*ico^*"inco c^CvfCMCOCOCO - H —i — * - - i - H ^-t ^ H —i CM CM CM CM CM CM CM CM CM CM CO CO CO CO CO CO COCMCMCMCMCM CMCMCMCJCMCMCMCMCMCMCMCMCMCMCMCMCMCMCMCaCM CMCMCMCM
33
S K JfcYCM CO CM •"*• --• -
SSKS^SS
CMO " 2
O C O 6 O O •"" O 8 O O O 8 i
C7>O 0 0 ) 0W UJ CO C7J Oi CD CJ> O)
CJ> /\ } 1 00 c_, /*\O O 0 O O 8 O O— O O «
, " ^ cv - w ^e
Coo
•^^^-rt-OCM
U O O O O O H - « ^ - H - i - 4 r t H - ( - i t \ ? W W W W W W OOOOOOOOOO—i^i—«W-H—<'—.^H-H-H—<CM OJCMCM CMCMCMCMCMCM OOOO—I-^-H—<_^_HLH—tCJCMCMCMCMCMCMCMCvICMCMCM.CMCMCMCMCMCMCVJCMCMOJ CMCMCMCMOJCMCMCMCMCMCMCMCMCMCMCMCvJCMCMCMCMCM CMCMOJ CMCXJCMCMCMCM OJCMCMCMCMCMCMCMCMCMCMCM
PART 1-1 25
IsotopeZ El A
91 Pa 215216217217m218221222223224225226227228229230
231232233234234m
235236237238
92 U 222226227228229230231232233234
235
235m236237238
239240242
93 Np 227?229230231232233234235236236m237238239240240m
241242242
94 Pu 232
Tl /2 orAbundance
14 ms0.20 s 44.9 ms 61.6 ms
0.12 ms6 fis
4.3 ms6.5 ms 100.95 s (5
1.8 s 31.8 m 2
38.3 m 322 h !1.4 d 417.4 d 5
3.276-10" y 111.31 d 227.0 d 16.70 h 51.17 m 3
24.1 n 29.1 m 28.7 m 22.3 m 1
1 /IS0.5 s 21.1 m 39.1 m 258 m 3
20.8 d4.2 d 168.9 y 4
1.592-105 y 22.45-105 y 2
0.0055% 5703.8-106 y 5
0.7200% 12
Decay Mode
aaaaaaaaaaa 74%, £26%a=85%, £=15%£=98%, a=2%£99.75%, a 0.25%£91.6%, 0-8.4%,awa, SF?0-, £=0.2%P-0-0-99.87%,IT 0.13%P- „P-, SFwP-P-aaaa>95Z, ££5%£=80%, a=20%a£, aO.006%a, SFwa, SFwa, SFw
a, SFw
=25 m IT2.3415-10' y M a , SFw
6.75 d 14.468-109 y 3
99.2745% 1523.50 m 514.1 h /16.8 n 560 s 5
4.0 m 24.6 m 348.8 m 214.7 n 336.2 m 14.4 d 1
396.2 d 12115-103 y 12
22.5 h 42.14-10° y 1
2.117 d 22.355 d 461.9 n 27.22 m 2
13.9 m 22.2 m 25.5 a /
34.1 in 7
fi-ll, SFw
0-0-P-SFa>50%, £<50%ES97%, a£3%£ 98%,a 2%£, a=0.003%£, as0.001%£
£, a 0.0014%£91%, 0-8.9%, a£52%, 0-48%a0~0~0-0-99.88%,1T0 12%0-0-0-C'vOU'O, Q'vCU/«
IsotopeZ El A
94 Pu 233234235236237237m238239240241242243244
245246
95 Am 232234235237238239240241242242m
243244244m245246246m247
96 Cm 238239240
241242243244245246
247248
249250
251252
97 Bk 240242
243244245246247248
248m249
250
Tl/2 orAbundance
20.9 m 48.8 h 1
25.3 m 102.851 y 845.3 d 20.18 s 287.74 y 424119 y 266570 y 6
14.35 v 103.763-10' y 12
4.956 h 38.08-107 y 10
10.5 h )10.85 d 2
55 s 72.6 a 2
0
73.0 n 1098 m 2
11.9 h 150.9 h 2
432.2 y 516.02 h 2141 y 2
7380 y 4010.1 h 1=26 it
2.05 h 139 m 3
25.0 m 222 n 3
2.4 h 1=2.9 h
27 d
32.8 d 2162.8 d 228.5 y 218.10 y 2
8500 y 1004730 y 100
1.56-107 y 53.40-105 y 3
64.15 m 3=7400 y
16.8 m 2<2 d5 m 2
7.0 m (3
4.5 h 24.35 h (54.94 d 31.80 d 2
1380 y 250>9 y
23.7 h 2320 d 6
3.22 h /
Decay Mode
£99.88%, a 0.12%£94%, a 6%£, a 0.0027%a, SFw£, aO.005%ITa, SFwa, SFa, SFw0-, a 0.0025%a, SFw0-a99.88%,SFO.12%0-P-£=98%, cc=2%, £SF£, a ?
£99.97%, a0.03%£, aO.0001%£ 99.99%, aO.01%£, awa, SF0-82.7%, £ 17.3%IT99.5%,aO.5%,SFwa, SFw0-/ ! - , £ *P-0-0-P-££90%, a s 10%
a>99.5%,°£<0.5%SFw£ 99%, a 1%a, SFwa 99.76%, t 0.24%a, SFwaa 99.97%,SF 0.03%aa 91.74%,SF8.26%P-SF=65%, a=28%,
P-P-£ , £ S F w
€ Ot ^ 1%
SF<0 03%£99.85%, a0.15%£, aO.006%f 99.88%,a0.12%£, a<0.2%
a>70%, 0-<3O%,
0-70%, £30%0-, aO.0015%,SFw0-
26 TULI
TABLE I (cont.)
IsotopeZ El A
97 Bk 251252
98 Cf 239240241242243244245246
247248249250
251252
253
254
255256
99 Es 243244245246
247248249250250m251252
253254254m
255256256m257
100 Fm 242243244245246247247248
249250
250m251252253254
255256
Tl /2 orAbundance
56 n 2
39 s +37-/1.06 a 153.8 m 7
3.49 m 1210.7 m 519.4 m 643.6 m 835.7 h 5
3.11 h 3333.5 d 28350.6 y 2113.08 y 9
898 y 442.638 y JO
17.81 d 8
60.5 d 2
1.4 h 312.3 in 12
21 s 237 s 4
1.33 a IS7.7 m 5
4.7 B 327 n 3
1.70 h 18.6 h J2.22 h 533 h J
471.7 d 19
20.47 d 3275.5 d 539.3 h 2
39.8 d 1225 m
K7.6 h
0.8 us 20.18 s +8-4
3.7 ms 44.2 s 131.1 s 235 s 4
9.2 s 2336 s 3
2.6 n 730 m 3
1.8 s5.30 h 825.39 h 53.00 d 123.240 h 2
20.07 h 72.63 h 2
Decay Mode
0-, a s 0.0001%
aa£=90%, a s 10%a, £?£586%, 0=14%a, t ?£=70%, a s 30%a, SF0.0002%,E<0.0001%£99.96%, aO.03%a, SF*a, SF*a 99.92%,SFO.08%a, SFwa 96.91%,SF3.09%0-99.69%,aO.31%SF 99.69%,aO.31%fi-SFrs70%, a>30%£96%, a 4%£60%, a 40%£90.1%, a9.9%,ESF£=93%, a s 7%r, a=0.25%t 99.43%, oO.57%££97%, a^3%£299%, a£l%£99.5%, a 0.5%a 76%, £24%,0-=O.Ol%a, SF*a0-99.59%,aO.33%, £ 0.08%0-92%, a 8%, SF0-0-
SF,a?aSF=99%,a=l%aa 92%, SF 8%a 50%, £ 50%
aa 99%, £=1%,SF=0.05%£=85%, (KB 15%a>90%,SF= 0.0006%,£<10%IT£98.2%, a 1.8%a, SF*f 88%,a 12%a 99.94%,SFO.06%a, SF*SF91.955, a 8.1%
IsotopeZ
100
101
102
103
104
105
El
Fm
Md
No
Lr
Rf
Ha
A
257
258259247248249250251252254254255256257258258m259
250251252253
254
254m255256
257258259
260252
253254255
256
257258259
260253?254?255?256?257258259
260?261
262?255?257
258259?260
Tl/2 orAbundance
100.5 d 2
380 MS 601.5 s 3
3 s7 s 3
24 s 452 s 6
4.0 m 52.3 m a10 m 328 m 827 n 276 m 45.2 h 555 d 443 a 4103 n
0.25 ms 50.8 s 3
2.30 s 221.7 m 3
55 s 5
0.28 s 43.1 m 23.3 s 2
25 s 21.2 BS60 B 5
O
=1 s
1.4 s=20 s22 s 5
28 s 3
0.646 s 254.3 s 55.4 s 8
180 s 30=1.8 s0.5 ms 2
=2 s=5 ms4.8 s 311 ms 23.1 s 7
20 us65 s 10
63 ms1.5 s
1 s
4 s1.2 s
1.52 s 13
Decay Mode
cx99.79%,SFO.21%SFSF
a£80%, a 20%a=70%, £=30%£94%, a 6%C£94%, as6%£>50%, a<50%££E 92%, a 8%£90.7%, a 9.3%£ 90%,a 10%acSF>95%, a<5%,£ ?
SF, as0.1%a, £=1%a 73.1%, SF26.9%a=80%, £=20%,SF=0.001%a>99%, £<1%,SF<0.06%ITa61.4%, £38.6%a99.7%,SF=0.25%aSFa 78%, £22%,SF<2%SFa=90%, £=10%,SF<1%a, SF<2%, £=1%a, £, SF<0.l7.a>70%, £<30%,SF<1%a>80%, £<20%,SF<0.03%a>85%, £<15%a>95%, £<5%a>90%, SF<10%,£<0.5%a, £?SF=50%, a=50%SF, a=0.3%a=50%, SF=5O%SFa=82%, £=18%SF=90%,a=10%a=93%, SF=6%,£=0.3%SF, o<10%a>80%, SF<10%,£<10%SFSFo=80%, SF=20%,
£?a, £SFas90%, SFs9.6%
PART 1-1 27
IsotopeZ El A
105 Ha 260261262
106 259?263
Tl/2 orAbundance
1.52 s 131.8 s 434 s 4
7 ms 30.8 s Z
Decay Mode
c<2.5%a>50%, SF<50%SF71%, a 27%,
SF=70%, a=30%SF=70%, a s 30%
IsotopeZ El A
107
109
261?262262m266^
Tl/2 orAbundance
1.5 ms 5115 as4 . 7 «s
5 ms
Decay Mode
as: 80%, SF=20%aaa
1-2. STANDARD MONITOR REACTIONSFOR NEUTRONS
Z. BODY*Nuclear Data Section,Division of Research and Laboratories,International Atomic Energy Agency,Vienna
Abstract
STANDARD MONITOR REACTIONS FOR NEUTRONS.The most important cross-section standards are given, both in the form of graphs and
numerical tabulations, from the Evaluated Neutron Data File/B-V (ENDF/B-V) evaluations.Remarks and comments are added on the status of these standards. Linear-linear interpola-tions should be used unless otherwise stated.
1. INTRODUCTION
Neutron cross-section measurements often require a determination of theneutron flux and this action can be the most difficult part of the experiment.The flux determination can be significantly simplified by the use of one of thecross-section standards, thus avoiding any complications associated with directneutron flux determinations.
It is essential that these cross-section standards be well defined, accuratelyknown, easy to use, easily referenceable and available without any difficulties.The IAEA International Nuclear Data Committee/(OECD) Nuclear Energy AgencyNuclear Data Committee (INDC/NEANDC) Nuclear Standards File provides justsuch a set of cross-section standards. There are about ten standards in the File,since in the case of a single standard, not all of the requirements can be ful-filled simultaneously at each energy point. Indeed, it is safe to say that there areas many compromises as there are standards. As a result, the user can choosewhich standard is the most acceptable. The choice will also be influencedby whether the user wants to measure a capture, a scattering or a fission cross-section, the ultimate decision being made in order to avoid experimental diffi-culties. With regard to activation standards, a further consideration in making achoice is that the half-life of the activity should be nearly the same as that of theactivity for the irradiated sample. If the half-lives differ considerably, then tempo-ral variations in the flux will not be properly taken into account by the standardmonitor (see also Part 2-2).
•Present address: Institute of Experimental Physics, Kossuth University, Debrecen, Hungary.
29
30 BODY
The following subsections detail the Evaluated Neutron Data File/B-V(ENDF/B-V) evaluations for the standards already completed, together with theENDF/B-V values for some recommended dosimetry standards. The latter arenot included as standards in the INDC/NEANDC Nuclear Standards File, thoughthey are very often used because of several advantages they possess (e.g. high spe-cific activity). The ENDF/B-V values presented are accompanied by some com-ments and remarks on the status of the particular cross-section in question, madeon the basis of information obtained at a recent meeting on neutron standardreference data1 and from papers referred to in the Computer Index of NeutronData (CINDA) master file up to April 1985. Version V of ENDF/B will hopefullybe changed to version VI in the near future, the latter being the outcome of asimultaneous evaluation using a generalized least squares program, R-matrixevaluations and a procedure for combining the results of the evaluations. Thesimultaneous evaluation process will provide cross-sections for the 6Li(n, t),10B(n, a,) , 10B(n, a), 197Au(n, 7), 2 3 5U(n, f), 238U(n, f), 238U(n, 7) and239Pu(n, f) reactions, while evaluations of 3He(n, p) and C(n, n) are beingperformed separately.
2. THE 1H (n, n ) ' H CROSS-SECTION
The hydrogen elastic scattering cross-section is currently the most accuratelyknown of all the standards. This cross-section can be determined from the totalneutron cross-section, which is easily measured and with which it coincides,except at low energies, where neutron capture makes a significant contribution[1,2]. A number of techniques have been employed in utilizing this cross-section.At low neutron energies (~ 1 keV to ~ 1 MeV), gas proportional counters havebeen used. Extrapolating the pulse height distribution of such a counter to zeroenergy and summing the events in the distribution yields a result which is directlyproportional to the product of the flux and the hydrogen cross-section. Thetiming jitter of these (both methane- and hydrogen-filled) proportional counterslimits their use in time of flight experiments in the MeV energy region. Protonrecoil telescopes represent the other extreme, in that their response is directlyproportional to the product of the flux and the cross-section for neutron-protonscattering into the appropriate solid angle of the detector. This can provide fasttiming, but suffers from low efficiency. A new scintillation detector [3] reportedrecently provides moderate efficiency with fast timing and small corrections [1].The ^ ( n , n) 'H cross-section is considered to be a standard between 1 keV and20 MeV [1].
1 IAEA-OECD/NEANDC, Nuclear Standard Reference Data (Proc. Advisory GroupMeeting Geel, Belgium, 1984), IAEA-TECDOC-335, IAEA, Vienna (1985).
PART 1-2 31
+ .005
bE_
O. POSS (1952)V HAFNER (1953)D FIELDS (1954)
— <r STORRS(I954)• OAT (1959)0 ENGELKE (1963)
i i i i 11 HI ro GROCE (I9S6)O DAVIS (1971)T SIMMONS (1971)A FUJITA (1976)
POENITZ(I98I)
-.005
-ml i i i i i i0.001 0.01 O.I 1.0
NEUTRON ENERGY (MeV)10 100
FIG. 1. Comparison between transmission measurements of the hydrogen total neutroncross-section and the Hopkins-Breit evaluation [1]. (Reference details for the individualslisted in this figure can be found in Ref. [I].)
S 6 0 -
E - 14.1 M*vI I 1 I ] I I I i I 1 I IT ALLRED (1953) • SUHAMIM967) —0 REMLEY (1953) a BASAR (1968)O SEAGRAVE (1955) » SHIRATO (1974)• NAKAMURA (I960) HOPKINS - BREIT _
i i i i i Mi l l I I0 30 60 90 120 150 180
CM. NEUTRON SCATTERING ANGLE (DEGREES)
FIG. 2. Hopkins-Breit evaluation compared with differential cross-section measurementsfor n-p scattering [1 ]. (Reference details for the individuals listed in this figure can be foundin Ref.[l]J
HOT 1301 CROSS-SECTIONS 1 -H - I
3 a s<
MeV
1-H - 1
ENERGY(eV
1.OOOOE-1.OOOOE2.OOOOE3.OOOOE4.OOOOE5.OOOOE6.OOOOE7.OOOOE8.5000E1.OOOOE1.1OOOE1.2000E1.3000E1.5000E1.7000E1.9000E2.OOOOE2.2000E2.4000E2.6000E2.8000E3.OOOOE
ELASTIC
SIGMA(b)
05 2.0449E0404040404040404050505050505
.9213E
.8126E
.7172E
.6327E
.5575E•4900E.4291E.3481E.2774E.2351E.1964E.1607E.0965E.0398E
05 9.8980E05 9.6710E05 9.2580E05 8.8920E05 8.5620E05 8.2620E05 7.9870E
01010101010101010101010101010100000000000000
ENERGY(eV)
3.2000E3.4000E3.6000E3.8000E4.OOOOE4.4000E4.8000E5.OOOOE5.5000E6.OOOOE6.5000E7.OOOOE7.5000E8.OOOOE8.5000E9.OOOOE9.5000E1.OOOOE1.1000E1.2000E1.3000E1.4000E
05050505050505050505050505050505050606060606
SIGMAIb)
7.7340E7.5010E7.2840E7.0830E6.897 0E6.5650E6.2750E6.1430E5.8450E5.5840E5.3540E5.1480E4.964 0E4.797 0E4.6450E4.5060E4.3780E4.2610E4.0510E3.8680E3.7060E3.5610E
00000000000000000000000000000000000000000000
ENERGY(eV)
1.5000E1.6000E1.7000E1.8000E2.OOOOE2.2000E2.4000E2.6000E2.8000E3.OOOOE3.2000E3.4000E3.6000E3.8000E4.OOOOE4.2000E4.6000E5.OOOOE5.2000E5.6000E6.OOOOE6.6000E
06060606060606060606060606060606060606060606
SIGMA(t
3.4290E3.3090E3.1980E3. 097OE2.9150E2.7590E2.6220E2.5010E2.392 0E2.293 0E2.203 0E2.1200E2.0430E1.9730E1.9070E1.8450E1.7340E1.6350E1.5890E1.5060E1.4300E1.3290E
>)
00 "00 "
ENERGY<eV)
r. OOOOE' . 5 0 0 0 E
00 8.OOOOE00 8.5000E00 9.OOOOE00 9.5000E000000000000000000000000000000 '<00
.OOOOE
.0500E
. 1000E
. 1500E
.2000E
.2500E
.3000E
.3500E
.4500E
.5500E
.6500E
.7500E
.8500E
.9500E>. OOOOE
060606060606070707070707070707070707070707
MAT 1301
SIGMA(b)
1.2690E 001.2010E 001.1390E 001 .0830E 001.0320E 009.8590E-019.4320E-019.0350E-018.6650E-018.3230E-018.0050E-017.7100E-017.4330E-017. 1730E-016.6980E-016.2740E-015.8930E-015.5490E-015.2380E-014.9550E-014.8230E-01
"0
FIG. 3. The 11 (n, n) cross-section (ENDF/B- V, Standards File).
34 BODY
TABLE I. UNCERTAINTY DATA FORTHE H(n, n) CROSS-SECTION
Energy range(eV)
1.0E+03 to 1.0E+05
1.0E+05 to 1.0E+06
1.0E+06 to 1.4E+07
1.4E+07 to2.0E+07
Correlation
+ 1.000
+0.339 +1.000
-0.110 +0.330
-0.040 -0.110
Uncertainty
(%)
0.5
0.7
0.9
1.0
matrix
+ 1.000
+0.335 +1.00
TABLE II. RELATIVE CENTRE OF MASS NEUTRON ANGULARDISTRIBUTIONS(Legendre polynomial form: sum over A(I)*P(I), 1=0, 1, 2, 3, 4; A(0) = 1.0;linear-linear interpolation [10])
E(lceV)
l.OE 00l.OE 022.OE 024.0E 026.0E 028.OE 02l.OE 032.0E 034.0E 036.0E 038.0E 03l.OE 041.2E 041.4E 041.6E 041.8E 042.OE 04
A(l>
+0.0000E 00-5.5958E-04-1.0415E-03-1.9165E-03-2.7587E-O3-3.5996E-03-4.3923E-03-7.8534E-03-1.3744E.02-1.9O07E-O2-2.3419E-02-2.7817E-O2-3.2412E-02-3.5926E-02-3.8681E-02-4.0592E-02-4.1766E-02
A(2)
+0.OOO0E 00+1.4582E-07+7.7858E-O7-8.2911E-06+2.2326E-05-2.O225E-O5-2.1837E-O5-1.4939E-04-3.9492E-04+3.5263E-04+7.5344E-O4+3.9395E-03+7.8464E-03+1.2899E-02+1.9119E-02+2.6532E-02+3.5148E-O2
A(3)
+0.0000E 00+1.0491E-11+2.4558E-14+8.8759E-09-1.583OE-O7-2.96O4E-O7-9.584OE-O7-3.2478E-O5-1.8595E-O4-5.7961E-O4-1.1913E-03-2.1302E-O3-3.3448E-03-4.6372E-03-6.O657E-O3-7.5378E-O3-8.9187E-03
A(4)
+0.0000E 00-6.2615E-12-7.1725E-12+9.1619E-10+4.0976E-09+1.3141E-08+5.5044E-08+1.3443E-06+1.6038E-05+4.5184E-05+2.7082E-04+4.2552E-O4+1.2151E-O3+1.955OE-O3+3.1383E-03+4.698OE-03+6.5867E-O3
PART 1-2 35
2.1. Status
Gammel [4] has analysed the available experimental data between 0 and40 MeV and provided a formulation for the ^ ( n , n) 'H cross-section which hasbeen used as a reference in many subsequent cross-section measurements [2].Newer experimental data were taken into account in a phase shift analysis byHopkins and Breit [5] and the resulting cross-sections were used in ENDF/B-II[6] and were retained in ENDF/B-III through V [7]. Neither the cross-sectionsnor the angular distributions have been changed since version II, except to addone more significant figure to the total cross-sections and to include correlatederror data and different interpolation rules [7].
Analysis of the neutron-proton interaction by Lomon and Wilson [8] differsfrom the Hopkins-Breit (HB) analysis by only <0 .3% at low energies (< 5 MeV)and thus this difference is well within the uncertainty range of 0.5-1.0% statedin the error files of ENDF/B-V. Dilg [9] measured the !H(n, n) *H cross-sectionat 135 eV and obtained a parameter set which results in cross-section values thatare within < 0.2% of those of ENDF/B-V [2].
In Fig. 1, transmission measurements of the hydrogen total neutron cross-section, with reported uncertainties of less than 1%, are compared with theHopkins-Breit evaluation. All experimental data in Fig. 1 agree with the respec-tive ENDF/B-V values within their quoted errors.
Above about 1 MeV, where proton recoil telescopes are used, angular distri-bution determinations are required [1]. In Fig. 2, differential cross-sectionmeasurements for n-p scattering at 14.1 MeV are compared with the Hopkins-Breit evaluation [5]. However, this cross-section has not been measured wellenough to determine the flux with 1% accuracy above approximately 10 MeV,nor can it be calculated with sufficient accuracy because of uncertainties inP-wave phase shifts [1, 10, 11]. High accuracy polarization measurements shouldprovide a more sensitive method for establishing the phase shifts. Recently, ana-lysing power measurements for n-p scattering have been performed by, for example,Tornow et al. [12]. Other similar measurements are mentioned in Refs [1] and [10].These analysing power measurements were successfully reproduced in the R-matrixanalysis of Dodder and Hale (see Ref. [1]), but the calculated total cross-sectionswere ~ 0.3% lower than those predicted by Hopkins and Breit [5]. The finalversion of this Dodder-Hale analysis was accepted in 1983 as the hydrogenstandard for ENDF/B-VI [13]. Figure 3. and Tables I and II detail the H(n, n)cross-section.
3. THE 3He(n, p) 3H CROSS-SECTION
The 3He(n, p) 3H cross-section is often used as a standard in the neutronenergy range from thermal to 50 keV. However, this cross-section is not acceptedas a standard in the INDC/NEANDC Standards File because of the lack of a good
25
24
23
22
21
20
18
17
16
15
14
13
12
11
10
9
8
7
6
5
3
2
1
\
i14\\\
A\\\\VV
- - 1 2 3 4 5 6 7
JHe (n.pl >H
— ENDF/B-V
| Borzakov et al (291
\ i
8 9 ^ W ElksV)
^ ^""m—•—r—
4t
47
46
45
44
43
42
41
40
39
— 38
37
36
35
34
33
32
31
30
29
29
27
~~r- 26
Ifla
\m
da\\
0.1 0,2 0.3 0.4 0.5 0.6 0.7 0.8( $ \
~ — . . M 1.0 E IkeVI
aO:o
11 12 13 14 1S 16 17 18 19 20 21 22 23 24 25 26 21 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49
E IkeV)
FIG. 4. The 2Hefn, p) cross-section: the ENDF/B-Vand the Borzakov etal. measurements.
PART 1-2 37
1.00
0.90
o.8o
0.70
TTT1 I 111
--*-.
o LOPEZ 1221• BOWMAN, LINAC [21]» BOWMAN, FILTEREO BEAM [211
HALE [231ENDF/B-V
_LLJ I I I I I
10° lO' 10' 10*NEUTRON ENERGY (eV)
FIG. 5. Various measurements of the 3He(n, p) cross-section [1].
detector. Development of a new detector at the US National Bureau of Standardswas reported at the 1984 IAEA-OECD/NEANDC Advisory Group Meeting in Geel,Belgium. If this development is successful, the situation might change [11].
3.1. Status
The data contained in version V of the ENDF/B evaluation were originallyproduced in 1968 and were accepted by the US Cross Section Evaluation WorkingGroup (CSEWG) Standard Subcommittee for version III in 1971, which in turn wascarried over intact again to version V [14] through version IV [15].
The thermal cross-section of 5327 b was derived from precise (better than1%) measurements by Als-Nielsen and Dietrich [16] of the total cross-section upto an energy of 11 eV. The 3He(n, p) cross-section was assumed to follow 1/v upto 1.7 keV. Gibbons and Macklin [17, 18] determined the 3He(n, p) cross-sectionfrom 5 keV and up. The ENDF/B evaluation was based on the results of themeasurements detailed in Refs [16-18] (at least for the thermal to 50 keV energyrange) and an error of 10% has been estimated for the recommended values [14, 15].Carlson [1] mentions that the uncertainty varies from 0.2 to ~4% from thethermal to 50 keV region. Wasson [19] ascribed errors of 3-5% in the ENDF/B-Vevaluation for the E < 1 MeV energy range, but these numbers have not beenuniversally accepted as being of reliable enough precision [20].
HRT 1 146 CROSS-SECTIONS 2-HE-3
101
O<
keV 2-HE-3
PART 1-2 39
i 2 _
I 10
I UJI Z •I UJ
<i S .
I O .
Si
— ~— — — — — — — — — — — o o o o o o o o o o o o o o o o o o o o o o o o o o o oOOiOGOOOOOOOOOOOOOOOOOOOOOOIOOOOOOOOOOOOOOOO:
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40 BODY
After the release of the ENDF/B-V evaluation Borzakov and co-workers [20]measured the 3He(n, p) cross-section for the neutron energy range from 0.15 to150 keV. Their experimental data are accurate to 2-3%. These new measurementsgenerally support [13] the lower values obtained by Bowman et al. [21] and Lopezet al. [22]. The preliminary evaluation by Hale [23] is in good agreement withthese measurements (see Figs 4 and 5)- It is apparent that the ENDF/B-Vevaluation is consistently higher at higher neutron energies compared with themore recent measurements. However, the new evaluation by Hale [23] appearsto better describe the 3He(n, p) cross-section [13]; Fig. 6 details the 3He(n, p)cross-section.
4. THE 6Li(n, t)4He CROSS-SECTION
The 6Li(n, t) 4He cross-section is a very important standard in monitoringneutron flux via detection of triton + a-particles by scintillation — glass, Lil (Eu),plastic foils - or by surface barrier detectors and ionization chambers [24].Reviews of detectors using this cross-section as a standard can be found in Refs[25-27]. In addition, it should be noted that tritium and/or 4He buildup can bea precise detection method [28], e.g. by using high sensitivity mass spectrometers[29-33]. The recommended energy range for use as a standard is thermal to100 keV [24].
4.1. Status
The low energy neutron cross-sections of 6Li - including the standard (n, t)cross-section - were obtained from a multichannel, multilevel, R-matrix analysisfor ENDF/B-V [34]. In the analysis, the database included the Harwell total cross-section [35], the shapes of the n-6Li elastic angular distributions and polarizations,6Li(n, t) angular distributions and (normalized) integrated cross-sections andfurther t-a elastic angular distributions [34].
Several new 6Li total cross-section data sets have become available since theevaluation of ENDF/B-V [36], but they differ from the previous data sets onlyabove 100 keV (at the region of the 240 keV resonance) and their influence onthe (n, t) cross-sections in the R-matrix fit together with new scattering cross-section data. New absolute measurements on the 6Li(n, t) cross-section werealso made, as mentioned in Refs [36] and [37]. The data of Gayther [38],measured relative to 23SU(n, f) at energies between 3 and 800 keV, agree ratherwell with the ENDF/B-V results if the ENDF/B-V values are also used for 235U(n, f).Renner et al. [39] measured the 6Li(n, t) cross-section between 80 and 470 keV;their data are also consistent with ENDF/B-V, except possibly for a small norma-lization difference [37]. The only value that was not quite consistent was thatmeasured by Engdahl et al. [40], which was obtained at 23 keV with a quoted
PART 1-2 41
TABLE III. UNCERTAINTY LEVELS OF THE 6 L i ( n , t ) CROSS-SECTION
DATA
Energy range
(eV)
Thermal to 2.000+2
2.000+2 to 2.000+3
2.000+3 to 1.000+4
1.000+4 to 3.000+4
3.000+4 to 1.000+5
Uncertainty given by Hale(Ref. [37])
(%)
0.4
0.5
0.5
1.0
2.0
Deviations from JENDL-3(Ref. [41])
(%)
0.5
0.7
1.0
1.4
1.7
uncertainty of 2.4%, 6% lower than the value of ENDF/B-V. Such a value is difficultto reconcile with the known resonances of the 7 Li compound nucleus [36].
In Table III, the uncertainties of the 6Li(n, t) cross-section data are given,specifically the uncertainty given by Hale [37] as well as the percentage differen-ces between ENDF/B-V and JENDL-3 [41] in different energy regions.
It should also be noted that even if the previous results of ENDF/B-VI [42]are taken as reference values, the outcome of a comparison with ENDF/B-V stilldoes not contradict the conclusion that below 2 keV the uncertainty level of thelatter is less than 1%, and between 2 and 100 keV it is at most 2% [19]. To sumup, the 6Li(n, t) cross-section below 100 keV is known reasonably well, thoughthe desired goal of 1% accuracy has not yet been achieved even at these lowerneutron energies [1]. Figure 7 and Table IV detail the 6Li(n, t) cross-section.
5. THE 10B(n, a) 7Li, 10B(n, a0) 7Li AND 10B(n, a ( ) 7Li* CROSS-SECTIONS
The 10B(n, «i)7Li* and the I0B(n, a0 + « ! ) 7 L i = 10B(n, a)7Li cross-sectionsare often used for neutron flux determination via, respectively, the detection ofthe isotropic 478 keV 7-emission of 7Li* in boron slab detectors and via the detec-tion of a-particles in ionization chambers with surface barrier detectors (or scintil-lators) [24]. A recent review of these detectors, using the above standards, hasbeen made by Carlson [43]. The recommended energy range for use as a standardis thermal to 200 keV for both cross-sections [24].
MflT 1303 CROSS-SECTIONS 3 - L I - 6
10'
. ltP
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00
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ksV 3 - L I - 6
1 3 - .U- 6 (N,T) MAT 1303
ENERGY(«V)
2.6410E-022.8702E-023.1031E-023...458BE-02.3.8129E-024.1695E-024.4038E-024.8792E-025.3371E-025.7729E-026.3719E-026.92076-027.5878E-028.3430E-029.2530E-021.Q00QE-Q11 .1127E-011 .2327E-011.3584E-011.4909E-011.6285E-011.7723E-011.9204E-012.0740E-Q12.2883E-012.5092E-012.7357E-012.9666E-Q13.2006E-013.5573E-013.9114E-014.2671E-Q14.7307E-015.1947E-015.6378E-016.2624E-016.6397E-017.3555E-018. 1746E-018.7847E-m9.5773E-011.0366E 00
SIGMA(b)
9.1601E8.7867E8.4506E8.0042E7.6235E7.2902E7.0936E6.7391E6.4435E6.1955E5.8971E5,6585E5.4040E5.1536E4.8936E4,7073E4.4625E4.2398E4.0388E3.355 IE3.6886E3.5358E3.3967E3.2685E3.J117E2.9715E2.8459E2.7329E2.6310E2.4956E2.3800E2.2786E2.1641E2.0652E1.9823E1.6809E1.8266E1.7355E1.6462E1 . RRROE1.5209E1.4619E
0202020202020202....;02 :
ENERGY(eVI
1.1522EI.2737EI.4021E
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02 2.6237E02 2.8525E02 3.Q852E.02 3.4368E02 3.7947E02 4.1477E02 4.5004E02 4.9727E02 5.4265E02 5.8574E02. ....6...44B3E.02 6.9884E02 7.6434E02 8.4134E.02 9.1724E020202Q20202020202 :02 .02 :02 .....02 '02 .02 .02 ;0202
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00000000000000000000000000000000000000.0000000000010101.010101010.10101010)01ot01010101
SIGMA(b)
1 .3866E1.3188E1.2569E1.2009E1 .1496E1 . 1029E1 .0600E1.0075E9.6068E9.1876E8.8113E8.4725E8.0272E7.6392E7.3068E
.7...Q.145E6.6730E6.3878E6.1483E
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ENERGY(eV)
02 5.1947E02 5.6379E02 eJ.2624E02 6.6397E02 7.3555E02 8.1746E02 8.7847E029.5773E01010101010101Q1
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01 2.1173E01 2.2925E01 2.5388E01 2.6873E.01 2.9682E01 3.2888E01 3.5270E.01 3.8357E01 4.2358E01 4.4694E01 4.9427E01 5.3.979E01 5.8303E01 6.4238E01 6.9668E01 7.6256E01 8.1603E01 9.0334E0101010101010101
.OOOOE
. 0905E1 .1764E1.294 IE
.4016E....531.9E1.6849E1.8357E
01010101010101010202020202020202020202Q20202020202020202020202.0202020303030303030303
SIGMA(b)
2.063OE1.9802E1.8788E1.8246E1.7334E1.6442E1.586 IE1.5190E.1 .4546E1.3947E1.3408E1.2922E.1.2275E1 . 1721E1.1235E
.K0686E1 . 021OE9.6116E9.3228E9..0613E8.6211E8.1896E7.9078E7..5824E7.2149E7.0235E6.6782E6.39Q0E6 . 1480E5.8567E5.6235E5 . 37.47.E5.1953E4.9375E4.6924E
. 4.4934E4.3261E4.1246E3.9632E
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010101010101010101010101010101or010000OQ0000000000000000000000QO00000000000000OQ0000
ENERGYlev
2.OOOOE2 . 181 OE2.4321E
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....1...5549E.1.7012E1.8446E2.OOOOE2.205 IE2.3976E2.6166E2.8663E3.00Q0E3.5000E4.OOOOE4.5000E5.Q0QQE6.OOOOE7.OOOOE8.OOOOE
...9.QQ00E1.OOOOE
03030303030303030303030303030303030304.04040404Q4040404Q404040404040404Q4040404
.04.05
SIGMA(b)
3.3175E 003 . 1772E 003.0092E 002.8754E 002.7334E 002.5943E 002.5035E 002.3988E 002.3131E 002.2194E 002.1196E 002,02136 001.9193E 001.8462E 001.7571E 001.6875E 001.6160E 001.5543E 001.4949E 001.4237E.001.3538E 001.3081E 001.2553E 00
.1...2.09 I E . 001.1591E 001.1159E 001.0743E 001....0275E. QO9.8897E-019.5095E-019. 1349E-018.9531E-Q18.3871E-017.9464E-017.5964E-017.3154E-016.9063E-016.6488E-016.5081E-016.4679E-Q16.5235E-01
>
s
FIG. 7. The bIJ(n, t) cross-section {ENDF/B-V, Standards File).
44 BODY
TABLE IV. UNCERTAINTY DATA FOR THE 6Li(n,t) CROSS-SECTION [37]
Energy range(eV)
I.OE-05 to2.0E 02
2.0E 02to2.0E 03
2.0E 03 to l.OE 04
l.OE 04to3.0E 04
3.0E 04 to l.OE 05
+ 1.00
+0.99 +1.00
+0.93 +0.96
+0.67 +0.72
+0.30 +0.35
Correlation matrix
+ 1.00
+0.88
+0.58
Uncertainty(%)
0.4
0.5
O.S
1.0
2.0
+ 1.00
+0.89 +1.00
5.1. Status
This ENDF/B-V [44] evaluation is the result of R-matrix analysis. The analy-sis considers simultaneously data from all the neutron interactions with 10B, as wellas measurements of the 4He+7Li system [1].
At present, the positions of these cross-sections are not very secure in the setof standards, though these ENDF/B-V values can be used for the time being. It ispossible that they are too low [ 1,45,46,42], and it is almost certain that the given uncer-tainties are too small. Wattecamps [47] has commented that these uncertaintiesare much smaller than the accuracies requested in WRENDA (World Request Listfor Nuclear Data) 81/82 and this is true also for WRENDA 83/84 [48]. Manyusers would like to see this cross-section have an accuracy of 1%.
In support of the above statements, it is appropriate to quote Poenitz:"Consideration of the 6Li+ n and 10B + n data bases shows that substantialprogress has been made for the 6Li(n, a) cross section but the 10B(n, a) and10B(n,o:1) cross sections remain poorly defined. There are few absolutemeasurements of these cross sections and those available have large uncer-tainties and/or are followed by various shortcomings. It is therefore recom-mended that the 6Li(n, a) cross-section should be used as a reference crosssection below 100-150 keV until a reasonable data base for the 10B + ninteractions becomes available." [36].
PART 1-2 45
Similarly, it was concluded at the 1984 IAEA-OECD/NEANDC AdvisoryGroup Meeting in Geel that the 6Li(n, t) and 10B(n, a) cross-sections both haveto be studied over a far wider energy range than that recommended in order tounderstand the reaction mechanism and to make accurate theoretical calculations.The experimental database for 6Li(n, t) has yielded results that are not very differ-ent from the ENDF/B-V data for En< 1 MeV, while the database for 10B(n, a)shows large disagreements between new and old measurements [11], especiallyfor10B(n, a j .
It is hoped that the forthcoming ENDF/B-VI evaluation will improve thesituation in the future [42]. Figure 8 details the 10B(n, a) cross-section, whileTables V and VI provide, respectively, the recommended reference data forthe I0B(n, a 0 ) and 10B(n. a,) cross-sections.
6. THE C (n, n) C CROSS-SECTION
The C(n, n)C cross-section is widely used primarily as a scattering standard,the relevant energy range being 1 keV to 1.8 MeV. While the presence of resonanceshinders the use of this cross-section as a standard above 2 MeV, it is useful up to4.8 MeV if care is taken to avoid prominent resonance structure. Since the capturecross-section is negligible above thermal energies and below 2 MeV, the elasticscattering cross-section is actually identical to the total cross-section. This standardis also very useful for verification of total cross-section measurements [49]. A slightuncertainty comes from the fact that the scattering cross-section of natural carbonis recommended as a standard, while R-matrix evaluations refer to the 12C(n, n)12Ccross-section (discussed below).
Carbon has several advantages over hydrogen as a scattering standard, one beingthe fact that the angular distribution in the laboratory system for carbon changesmore slowly with angle than it does for hydrogen. Also, there is reduced energyloss and more simplified multiple scattering corrections for carbon compared withhydrogen [1, 13]. In addition, it should be noted that the energy of the 2078 keVresonance is a valued energy-scale reference point [50].
6.1. Status
The ENDF/B-V evaluation is taken from the R-matrix fits of Fu and Perey [51 ].Concurrent with this work, Holt, Smith and Whalen have reported new neutrontotal and scattering measurements, together with an R-matrix interpretation [52].The latter work is consistent with that of Ref. [51 ] and supports the ENDF/B-Vevaluation to accuracies of < 1% [50]. Recent precision neutron total cross-sectionmeasurements by Poenitz and Whalen [2, 50] (shown in Fig. 9) verify theENDF/B-V file to fractional per cent accuracies [50]. The new evaluation forJENDL-3 [53] differs from that of ENDF/B-V by a negligible amount only below5 MeV.
4
MRT 1305 CROSS-SECTIONS 5 -B -10
tdO'©
keV 5 - B - 1 0
1 5-B - 10 (M. ALPHA) MAT 1305
ENERGYleV)
SIGMA
2.4030E-02 3.9367E2.6410E-02 3.7551E2.87Q2E-Q2 ;3. 1031E-02 C3.4588E-02 C3.8129E-02 C4.1695E-Q2 24.4038E-02 24.8792E-02 25.3371E-02 '.5.7729E-02 26.3719E-02 ;6.9207E-02 :7.5878E-02 :8.3430E-02 59.2530E-02 '.
.0000E-01
. 1 127E-01
.2327E-01
.3584E-01
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.7723E-01
.9204E-012. 0740E-012.2883E-012.5092E-OI2.7357E-012.9666E-0I3.2006E-013.5573E-01
).6020E).4642E1.2812E). 1251E!.9885E>.9079E'.7626EJ.64 14E!.5397£>.4174E>.3195E>.2152E>. 1126E>.0060E.9296E.8292E.7379E.6555E.5802E.5119E.t493E.3922E.33U7E.27'jiE. 2 1 7<)E.1664E.1201E. 0783E.0228E
3.9114E-01 9.7541E4.2671E-01 9.3385E4.7307E-0I 8.0690E5.1947E-0) 8.4G35E5.6378E-01 8.1239E6.2624E-01 •6.6397E-017.3555E-01 '
r.7080Er.4857Er. 1 I20E
8.1746E-01 6.7462E8.7847E-01 6.50/6E9.5773E-01 t
.0366E 00 E1.1522E 00 f1.2737E 00 E
>. 2324E>.9903E>.G8I6E>.4 03GE
(bl
030303030303 J03 ;03 :03 :03 C
ENERGY(eV)
.402 IE
.5359E,676 IE.8209E.9714E
>. 1820E>.3998E>.6237E>.8525E1.0852E
03 3.4368E03 :03 '03 t03 <•
).7947E.1477E
I.5004EI.9727E
03 5.4265E03 5.8574E03 6.4483E03 6.9884E03 "r.6434E03 8.4134E03 9.1724E0303030303030303
.00O0E
.1127E
.2327E
.3584E
.4909E
.6285E
.7723E
.9204E03 2.0740E02 2.2883E02 2.5092E02 2.7357E02 2.9666E02 3.2006E02 3.5573E02 3.9114E02 4.2671E02 <02 '
I.5004EI.9727E
02 5.4265E02 E02 e02 C
).8574E>.4483EJ.9884E
0000 <0 0 <•00 '
SIGMA(b)
i. 1498E1.9202EI.7097EI.5183E
00 4.3422E00 '1.1271E00 3.9351E00 3.7633E00 3.6090E00 3.4701E00 3.2876E00 3.1285E00 2.9923E00 2.8725EOQ 2.7325E00 2.6156E00 2.5175E00 2.3992E00 2.3045Eoo :oo :oo :010101010101010101010101010101
2.2O35E2. 1001E2.O112E.9261E.8256E.7342E.6517E.5763E.5080E.4453E.3883E•3357E.2714E.2 139E.1624E. H61E.0744E.0189E
01 9.7151E01 9.2999E01 9.0548E01 f3.6125E01 8.2432E01 "01 '
f.9331EP.5596E
01 7.2605E
02
ENERGY(eV)
?.6434E02 8.4134E02 9.1724E020202020202020202 :
.0000E
.1 127E
.2327E•3584E.4909E.6285E.7723E.9204E
J.074 0E02 2.2883E02 :02 :02 :02 :
2.5092E2.7357EJ.9666E3.2006E
02 3.5573E02 3.91HE02 '02 '02 '02 '02 '
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02 6.4483E02 6.9885E02 "02 (
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02 9.1724E020202020202020201010101oi :
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.4909E1.6285E1.7723E1.9204E2.O74OE2.2883E2.5092E2.7357E2.9666E
01 3.2006E01 3.5573E01 3.9114E
01 e01 e01 f.02 e02 E02 E02 E02 102 102 102 <02 *02 C02 C02 :02 ;02 ;02 C02 C02 :02 :02 :02 :02 :02 502 502 ;02 :02030303030303030303030303030303 £03 £
SIGMA(b)
>.9414E.6150E•3344E.0657E.7472E.4576E. 1965E..9579E.7417E.5434E•3629E.1967E.9934E
I.8118E>• 649 I.E.I.5028E).3710E1. 1959E).0464E>.9154E!.8380E'.6986E!,5822E'.4844E.3667E.2725E.1720E
'.0693E.9809E•8964E,7960E.7048E.6226E.5475E•4795E.4172E.3604E.3082E.2443E.1873E.1362E.0903E.0490E
) .94 04E).4718E
01 <01 <01 .t01 E01 E01 e01 t01 "
ENERGY(oV
I .2671E.5004E,9727E
).4265E).8574E).4483E),9884E.6434E
01 8.1746E01 9.0413E0101010101oi0101
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01 2-OOOOE01 2.2134E01 2.4573E01 2.6388E0! 2,8744E01 3.1098E01 CJ.4024E01 3.6891E01 '01 '01 '
1. OOOOEI.4102EI.7951E
01 5.2332E01 5.7327E01 6.2357E01 6.7354E01 "r.4833E01 8.2391E01 9.OOOOE01010101010101oo :00
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Ibl
03 9. 0612E03 8.8190E03 8.3822E03 8.0178E03 "03 •03 "
'.7119Er.3438Er,Q491E
03 6.7349E03 6.5085E03 6.1831E04 5.8739E04 5.6232E04 5.4126E04 5.1589E04 i04 '
I.9557EI.7388E
04 4.5170E04 4.3262E04 '».., 1435E04 3.9412E04 3.7429E04 3.6134E04 3.464 0E04 3.3330E04 3. 191 OE04 3.0684E04 2.9505E04 2.8167E04 2.7 068E04 2.5975E04 2.4890E04 2.3936E04 2.3100E04 2.2012E04 2.1068E04 2.0243E0505050505050505
.9304E
.8528E
.7783E
.6871E
.6066E
.5123E
.4 075E
.1568E
000000000000000000000000000000000000000000000000000000000000000000000000000000000000QO00
===
FIG. 8. The i0B(n, a) cross-section (ENDF/B-V, Standards File).
48 BODY
TABLE V. RECOMMENDED REFERENCE DATA FOR THE 10B(n, <x0)CROSS-SECTION(numerical values are from ENDF/B-V, MAT-1305; applicable energy range:thermal to 200 keV; log-log interpolation [47])
E
1.1.1.2.5.8.1.1.
(keV)
OOE-0800E-04OOE-O100E 01OOE 0100E 0120E 0280E 02
XSEC (b)
11321111
.228 7E 04
.2285E 02
.8622E 00
.7184E-O1
.7988E-01
.4919E-01
.3121E-01
.2458E-01
Cross-section
E
11136912
(keV)
.00E-05
.OOE-03
.OOE 00
.OOE 01
.OOE 01
.OOE 01
.4OE 02
.OOE 02
values
XSEC (b)
3.3.1.2.1.1.1.1.
8853E 02883OE 012092E 002520E-01668OE-O14307E-012707E-012495E-01
E
2114711
(keV)
.53E-O5
.00E-02
.OOE 01
.OOE 01
.OOE 01
.OOE 02
.60E 02
XSEC (b)
2131111
.4425E 02
.2263E 01
.8004E-01
.9802E-01
.5690E-01
.3819E-01
.25O6E-O1
Uncertainties
ENERGY RANGE (keV)
1.0E-08 TO 4.0E 014.0E 01 TO l.OE 02l.OE 02 TO 1.8E 021.8E 02 TO 2.0E 02
UNCERTAINTY (PER CENT)
2.22.01.21.6
CORRELATION MATRIX
+1.000+0.924+0.055+0.316
+1+0+ 0
.000
.323
.302+ 1+0
.000
.627 +1.000
PART 1-2 49
TABLE VI. RECOMMENDED REFERENCE DATA FOR THE 10B(n, a jCROSS-SECTION(numerical values are from ENDF/B-V, MAT-1305; applicable energy range:thermal to 200 keV; log-log interpolation [Al])
E (keV)
1.00E-081.00E-04l.OOE-012.00E 015.00E 018.00E 011.20E 021.80E 02
XSEC (b)
1.8071E1.8067E5.6795E3.8717E2.4736E1.9859E1.6471E1.3442E
0503010000000000
Cross-section values
E (keV)
1.00E-051.00E-031.00E 003.00E 016.00E 019.00E 011.40E 022.00E 02
XSEC (b)
5.7142E5.71O9E1.7754E3.1664E2.2697E1.8812E1.53O7E1.2626E
0302010000000000
E (keV)
2.53E-051.00E-021.00E 014.00E 017.00E 011.00E 021.60E 02
XSEC (b)
3152211
.5923E
.8035E
.4939E
. 7524E
.1124E
.7922E
.4320E
03020000000000
Uncertainties
ENERGY RANGE (keV)
1.0E-08 TO 4.0E 014.0E 01 TO 1.0E 021.0E 02 TO 1.8E 021.8E 02 TO 2.0E 02
UNCERTAINTY (PER CENT)
0.30.70.81.2
CORRELATION MATRIX
+1.000+0.981+0.861+0.729
+1.000+0.928+0.810
+ 1+0
.000
.921 +1.000
50 BODY
3.0
2.0
n i 1111
CTOT
e
1.00.02
PRES. EXPENDF/B-V
1 1 I I I I I I I0 10 1.0 2.0
E. (MeV)
FIG. 9. Comparison of the neutron total cross-sections of natural carbon, as measured byPoenitz and Whalen, with the corresponding values given in the ENDF/B-V file [50].
It should be noted that all data considered in Ref. [51 ] are for natural carbon(containing 1.11% 13C), while the analysis is for 12C. There are two resonancesin 13C below 2 MeV and each resonance will still contribute about 0.2% to thenatural carbon cross-sections. Therefore, the energy ranges from 0.13 to 0.18 MeVand from 1.72 to 1.78 MeV are not recommended as standards until sufficientlydetailed investigations are carried out for these resonances [51 ]. In the upcomingENDF/B-VI evaluation for natural carbon, the contribution to the elemental cross-section from the 13C resonances at 153 keV and 1.75 MeV will be included in theR-matrix analysis [1]. Figure 10 and Tables VII and VIII detail the C(n, n) cross-section.
7. THE 27Al(n, a)24Na CROSS-SECTION
This activation cross-section is a Category-I dosimetry reference and is widelyemployed as a standard in dosimetry and activation measurements [54]. TheENDF/B-V evaluation is recommended for the energy region from ~ 11 to 20 MeV.
PART 1-2 51
7.1. Status
This ENDF/B-V evaluation was made by Hale, Stewart and Young [55].The evaluation agrees with that of Tagesen and Vonach [54, 56] within the givenerrors. Except for the low threshold region at 8-9 MeV, the accuracy of theTagesen-Vonach evaluation was claimed to be better than 5%. In particular, anaccuracy of about 0.5% was estimated for the 13.5-14.8 MeV region [57]. Evainet al. have used the results of the Tagesen-Vonach evaluations [58] as well as theevaluations of Winkler and Ryves [59] and Ryves [60].
Recently, a new evaluation was performed by Kornilov et al. [61], therecommended data cf which are plotted in Fig. 11, while the assigned errorscan be found in Table IX. In the figure, the cited evaluations were plottedtogether with the results of those measurements which were not included in theevaluations (to renormalize the results of Garlea, ENDF/B-V values were usedfor the 235U(n, f) cross-section). It can also be seen from this figure that ENDF/B-Vagrees well (within 5%) with the experiments and evaluations cited, except in theneighbourhood of the threshold. However, in the 14 MeV region, ENDF/B-V mightpossibly be higher by approximately 1-2% than the majority of the experimentalvalues. In the table, the lower and upper limits of uncertainty mean the ± uncer-tainties 'at least' and 'at most', respectively.
In Fig. 12 , the ratios of the ENDF/B-V (dashed-dotted line) and Tagesen-Vonach (dashed line) evaluations are contrasted with the evaluation of Kornilovet al. It should be noted, however, that there is an apparent presence of structurein the evaluation by Kornilov et al. from 6 to 8.5 MeV which must be taken intoaccount in the use of this cross-section. It was recommended at the 1984 IAEA-OECD/NEANDC Advisory Group Meeting in Geel that the reasons for the differen-ces in the Vonach and Kornilov evaluations should be fully investigated [11].Figure 13 and Table X illustrate and detail the 27Al(n, a) cross-section.
8. THE s6Fe(n,p)S6Mn CROSS-SECTION
The cross-section standard 56Fe(n, p)56Mn is frequently used to measurefast-neutron fluence rates, especially around 14 MeV. The 27Al(n, a) or theS6Fe(n, p) cross-sections are clearly the references for the majority of measure-ments where a monitor-foil or mixed-powder technique is employed and themeasured quantity is, in fact, a ratio of cross-sections. However, it should benoted that the 56Fe(n, p) cross-section was not accepted as a standard at the1984 IAEA-OECD/NEANDC meeting in Geel because the standard cross-sectionof the 27Al(n, a) reaction is available in the energy region of interest. Neverthe-less, the activation of natural Fe may be used as a reference, taking advantageof the higher specific activity. For this purpose, an evaluation was stronglyrecommended [11]. The present version of the ENDF/B-V evaluation is recom-mended for the energy region from ~ 11 to 20 MeV.
HflT 1306 CROSS-SECTIONS
.ELfiSTIC
FTT 10,-10 10",-9 10 10 10" 10""MeV
10 10"
4 .5
1.0
3.5
3.0
2.5
2 .0
1O"2 10 ' 10°6-C -NPT
O
1 6-C - 0 ELASTIC MAT 1306
ENERGY SIGMA ENERGY SIGMA ENERGY SIGMA ENERGY SIGMA(eV) (b) (eV) (b) (eV) (b) (eV) (b)
1.0000E-05 4.7392E 00 4.0000E 05 3.6182E 00 8.5000E 05 2.7888E 00 1.3500E 06 2.1739E 002.0QQ0E 04 4.6653E 00 5 . QQOQE 05 .3.4Q33E OQ 9 . 7500E...05. ..2..61.08E.. .00 1...475.QE.. 06 , 2 . Q552E. 0.01.0000E 05 4.4084E 00 6.0000E 05 3.2076E 00 1.1000E 06 2.4503E 00 1.6250E 06 1.9277E 002.0000E 05 4.1172E 00 7.2500E 05 2.9868E 00 1.2250E 06 2.3052E 00 1.7750E 06 1.8155E 003,0000E 05 3 .855 IE OQ
5
FIG. 10. The C(n, n) cross-section (ENDF/B- V, Standards File).
OJ
54 BODY
TABLE VII. UNCERTAINTY DATA FOR THE C(n, n)C CROSS-SECTION [50]
ENERGY RANGE (keV) UNCERTAINTY (PER CENT)
12505006007007508009001000110012001280130014001500160017001750
TOTOTOTOTOTOTOTOTOTOTOTOTOTOTOTOTOTO
25050060070075080090010001100120012801300140015001600170017501800
0.460.460.530.530.530.530.530.530.530.530.530.530.530.530.600.600.600.60
CORRELATION MATRIX (PER CENT)
1003833333333333333333333333329292929
10033333333333333333333333329292929
100717129292929292929292925252525
1007129292929292929292925252525
10057292929292929292925252525
100717129292929292925252525
1007129292929292925252525
10029292929292925252525
100717129292925252525
1007129292925252525
10057292925252525
100717125252525
1007125252525
10025252525
1007 7 10077 77 10022 22 67 100
PART 1-2 55
TABLE VIII. RELATIVE CENTRE OF MASS NEUTRON ANGULARDISTRIBUTIONS [50](Legendre polynomial form: sum over A(I)*P(I), 1=0, 1, 2, 3, 4, 5; A(0) = 1.0)
E <keV) AU> A(2) A(3) A(4) A(5)
.1000E 01
.5000E 01
.1000E 02
.5000E 02
.1000E 03
.2000E 03
.3000E 03
.4000E 03
.5000E 03
.6000E 03
.7000E 03
.8000E 03
.9000E 03
.1000E 04
.1100E 04
.1200E 04
.1300E 04
.1400E 04
.1500E 04
.1600E 04
.17OOE 04
.1800E 04
.1850E 04
.1900E 04
.1925E 04
.1950E 04
.1960E 04
.197OE 04
.1980E 04
.1990E 04
.2000E 04
.42O3E-O3
.2O95E-O2
.4173E-O2
.2O18E-O1
.3876E-01
.7164E-01
.9948E-01
.1230E-00
.1426E-00
.1588E-00
.1718E-OO
.1819E-00
.1892E-00
.1939E-00
.1961E-00
.1957E-OO
.1927E-00
.1869E-00
.1784E-00
.1666E-00
.1511E-00
.1311E-00
.1187E-00
.1O38E-OO
.9486E-01
.844SE-01
.7965E-01
.7437E-01
.6846E-01
.6171E-O1
.5385E-01
.3749E-O3
.1397E-O2
.4868E-02
.9585E-02
.1498E-01
.2O65E-O1
.2636E-01
.3196E-01
.3742E=01
.4275E-O1
.48O7E-O1
.5355E-O1
.5945E-O1
.66O5E-O1
.7385E-O1
.834OE-O1
.953OE-O1
.1104E-00
.1295E-OO
.14O7E-OO
.1531E-OO
.1596E-00
.1665E-0O
.1693E-OO
.1723E-0O
.17S4E-OO
.1788E-OO•1827E-OO
.4437E-03
.8995E-03
.1569E-02
.2444E-02
.3498E-02
.4679E-O2
.5912E-02
.7091E-02
.8092E-02
.8736E-02
.8792E-O2
.7973E-O2
.5893E-02
.1978E-O2
.4672E-O2
.1583E-01
.2433E-01
.3641E-01
.4474E-O1
.SS65E-O1
.6109E-01
.6 738E-O1
.74 76E-O1
.8365E-01
.9457E-01
.514OE-O3
.9234E-03
.1549E-02
.2463E-O2
.3 750E-O2
.551OE-O2
.785OE-O2
.1088E-01
.1471E-O1
.1939E-01
.24 78E-O1
.3022E-01
.3225E-01
.3267E-01
.3155E-O1
.2866E-01
.267OE-O1
.2408E-01
.2053E-01
.1571E-O1
.9072E-O2
.6801E-03
.9821E-03
.1388E-02
.1923E-02
.2604E-02
.2998E-O2
.3410E-02
.3610E-02
.3789E-02
.3850E-02
.3900E-02
.3934E-02
.394 7E-O2
.3927E-O2
56 BODY
" A l Ins) "Na
EVALUATION:
ENDF/8-V
+ Tagcsen-Vunach
• Winklcr-Ryves
o Kornilov pt al
MEASUREMENT:
• Li Jizhou
7 Antonov et a{.
• Garlea et at.(renormatized)
• Enz el al.
t Enz et al.(with pulsed beam]
x Kudo et al.
REF
IS6I
1591
1611
[621
1631
I6t]
16SI
[65]
[66!
FIG. 11. Different measurements and evaluations for the 1Al(n, a.) cross-section.
TABLE IX. UPPER AND LOWER UNCERTAINTY LIMITS FOR THE27Al(n, a) REACTION CROSS-SECTION [61]
Energy region(MeV)
5.5-6.0
6.0-8.5
8.5-11
11-13.5
13.5-15.5
15.5-17.5
17.5-20.0
Lower limit of uncertainty
15
5
0.8
0.7
0.6
0.9
1.4
Upper limit of uncertainty
15
5
3.8
5.8
2.5
4.1
7.6
PART 1-2 57
1.08
1.06
1.04o5 1.02
o6
0.98 •
0.96
0.94
V\
\
A // V
A' \
s
/
/ /,• /
/ // • /
/
/
/
A " " * -/ V
"• - \ / \
\
\
V
//
11
\
\\
\
, \\ ^
\ '
/
/.\
\
1 1
10 12 14 16
En(MeV)
18 20 22
FIG. 12. Cross-section ratios of the ENDF/B-V (dashed-dotted line) and Tagesen-Vonach(dashed line) evaluations compared with the evaluation of Kornilov [61].
8.1 Status
This ENDF/B-V evaluation was carried out by Fu [67] based on work byDudey and Kenneriey [68], Smith and Meadows [69] and on other experimentaldata that were current at that time.
In Fig. 14, the ENDF/B-IV and ENDF/B-V values are plotted as curvesand are supplemented by more recent experimental data which have errors ofless than 5% (these data were not included in ENDF/B-V). For the 14 MeV(and upper) energy region, the new data are, in general, above the ENDF/B-Vcurve (they are higher by about 4% on average). Particularly interesting are thevalues of Fu et al. [70], who carried out a simultaneous evaluation of the 32S(n, p),56Fe(n, p) and 65Cu(n, 2n) cross-sections, the input evaluations being those theyhad previously submitted for the ENDF/B-V Dosimetry File (Table XI).
Concern has been expressed that ENDF/B-V data are too low in the lowerenergy region. Raics et ah, for example, have measured cross-sections of the56Fe(n, p) and other reactions relative to the 238U(n, f) reaction in the 6.5-10.5 MeVregion and calculated normalized X values for different data sets. Basedon these calculations, they concluded that at an acceptance level of 97.5%, twoof the data sets they examined could not be used for the 238U(n, f) reaction, norcould ENDF/B-V be used for the S6Fe(n, p) reaction in the 6.5-10.5 MeV energyregion. It was their belief that ENDF/B-IV was the most acceptable and consistentdata set for the 56Fe(n, p) and 238U(n, f) reactions [75].
MRT 6 3 1 3 CROSS-SECTIONS 1 3 - A L - 2 7
60O-O
MeV 13-(lL-27
Ito
a.
II tnenentntnentiUJientnoKJitnentnitntntntntnn • 'nnII cooo<Ood3obtoooo<J>oocn:-> _II rnmmiTimmmmmmm-:mmm mmmmrnrnII : iu ooooooooooooooooooooII cncncnicncncncn'cncncno-cncncncnocncncnen
I tn.b.b{OCOCOCOiS3K3S3S3iS3-
co co cn<0 en co —<» tn co sso oo-J ^<JO s s — o en
o -4 cn;—»co <O -»;M tn .k-co A .& JV .^ en i en ACC-S3COCnui(OCO:S3COO~J:COCO-» - £ * S 3 O Cn-«JCOm m mm m m rrvm m m m;m m m m;m m m m mI I I I I I ! I I I ! I I I I I I I I I
O O OO O OOSOOOOOOOOOOOO
en cn<j> en en t w o tn tn enitn en 01 t n m tn en 01 en
•J tn ;^ CO S3— o C0 CO COCO tO CO 03O3 03 CO ] ^J
— II~2~ n- II
O O O O O O O O G ) JO O O O O O O 00 CO COA 01K3-J 03 O 010-JmmTTinimm^Tinimrn.:mmmm;rniTi mrnmooooooooooioooooooooo) o o i O)0 )O I< ] IO)0 ] G > O cn O) o o o> o o> o
co axji -b to ro;- * (O coioo J J ai tnC D t O C O b ^ C O N5:-> o O C D — O l — M - J•«J :•& o <o * to co w a*tn a> tn co I D -C» OO O - J
^ J k O C O C O ( O C O O > CO O O O O O O J O : O O O O C > C no o o o o o o tn to C0:Ji co -J ro:^ ocotn —*m rrrm rn m m:m m rn m=m m m rri:m m mm mi i : i i i i • i i i i • i I i i • i i i i i
O O O O O OO O O OiO O O O O O O O OCO CO 4 0 CO CO COW CO CO COiCO CO A A i A £» .£* i k A
_. — < 0 CO CO tDiCO 03 00 00:00 0 0 - J « J ~ J - 4 - J O 5 O>
o oco a> .& K5:o co en .&iio o a> a*.e» so o t o c oUIOOOOOO OOOO 0 0 0:0 OOOO0 0000000000000:00 OOOOOOOO OO O O OO O O 0:0 OOOOm m;m m m m:m m m ntm m m m-m m mrn mooo oooo ooobooooo oo oM •NJO O) en cnicn o> en cnicn en c> CDicn en o>oi en
m 11 >
ilz(S> II r
i!!= > it •
uIIIIIIIIII
m II_ Z ilo m n< 33 II
d II< n
11to n• - 1 U
il ?it —IIiln
S »S> il
iln
tocoiooco-J~i;-4cnentnJAi»cocois3S3-«---" ,{
to-.>jcotOtnoJitoco;--i-'aioitnotnto-- I]CnS3~JC0-J-'S3t0S3C0i-'C0CnoiO — tD-J03 II-•000000000000000000 IIS3 OOOOOOO OOOOOOOOOOOm mTn m m m:m m m m;m m m rrvm m mrn m1 1:1 1 1 1 1 1 1 111 1 1 1 :1 1 1 1 1o 00 o o 00 oooio oooo ooooS3 S3 JO S3 S3 S3iS3 S3 S3 S3iS3 S3 S3 S3 S3 S3 S3 S3 IO
II II11 m 11H _ 2 II11 » m 1111 < 33 11n a n11 < 11
11u11
n
o coco oo 03 ~)-J en en tnwi Jk A coco sj K J - • - .ocnotnotnotnotnotnotnotnouiooo.o ooo ooooooooo ooooO OO O O OO O O OiO OOO OOOOOm mtn m m m;m m m m m m m firm m m rOOO OOOO OOOOOOOiO OOOO
II (/I ||•I ___ •—• Itii £. o IIil 2 Hil > ilil ilII II
nII
m II_ — 2 IIII 5- m »II S 33 IIII CD II
(j} A !A tn a> ~Ji~) co to -
00C0<0CJ)CO->(003~J O i — - • S 3 I O S 3 S 3 K 3 - > oo •& co e n - J - . .£> .tk o t n x > CD •& CD e n - . i v ~4O COO CO O COO O O *><D CO -«J COCO O N3SO t no*Jo*Jo>]ooio -»ocno o-£i ocoom mtn m m m:m m m m;m m m m-m m mm mi i: i i i i i i i i: i i i i: i i i i iooooooooo oo o o oo o oooS3 S3N3 S3 S3 S3 S3 S3 S3 — - • — - • ->•-» — ——• —
•< IIIIII
I?
IIIIIIIIIIIIII - .II CO u11 . —1 n en11 a- a 11 co11 ~ S 11 - •n s> 11 co
6S Z-\ XHVJ
60 BODY
TABLE X. UNCERTAINTY DATA FORTHE 2 7Al(n, a) CROSS-SECTION
Energy range(eV)
5.4E+6 to 5.9E+6
5.9E+6 to8.0E+6
8.0E+6 to 9.0E+6
9.0E+6to 1.0E+7
1.0E+7to 1.1 E+7
l.lE+7to2.0E+7
Uncertainty(%)
30
25
23
22
21
5
TABLE XI. INPUT-OUTPUT DATA SETS FOR THE 56Fe(n, p) REACTION [70]
E(MeV)
10
13
16
Input data set
XS(mb)
69.3
112.0
81.8
STD
(%)
4.0
2.5
2.0
Output data set
XS(mb)
71.0
114.3
85.0
STD
(%)
3.4
1.9
1.1
Lu Hanlin et al. [76] have concluded that between 5 and 8 MeV, the Chinese evalu-ation is about the same as ENDF/B-IV. Between 8 and 12 MeV, their curve is situatedroughly at the half-way point between ENDF/B-IV and the evaluation of Simonsand McElroy [77], the difference between the lowest curve (see Ref. [68]) andthe highest curve [77] being about 7%. For the 12 to 20 MeV energy region, theevaluation of Lu Hanlin et al. is higher than that of ENDF/B-IV, indirectly implyingthat their curve is also higher than the ENDF/B-V curve. Evain et al. [58] alsoappear to believe that ENDF/B-V is too low, since they use an ENDF/B-V shape,but normalize it to the (higher) Ryves value.
As a result of the above criticisms concerning ENDF/B-V, it is recommendedthat only values higher than 11 MeV be used in this file. Furthermore, it is suspectedthat uncertainties somewhat higher than the presented ones would be more reliable.Figure 15 and Table XII detail the 56Fe(n, p) cross-section.
PART 1-2 61
•s 1
118
m
m.
112
110
108
106
W.
102
100
Y / ENOF/B-IV
s^ ENDF/B-V ^ ^ ^
EVALUATIONS- %. \ .
ENDF/B-V \ v '••.
ENOF/B-IV N. \
i - Fu et at 1701 N. \
• Winkler-Ryves 1591 \ \
MEASUREMENTS: N ^
A Lu Hanlin et al. 1711 \ \
_ Sharma et al 1721 \ N .
Ryves et al. 1731
• Antonov et al. 163]
• Kudo et al. {661
T Pepelnik et al. [741
\
\
• \
13 13.2 13.t 13.6 13.8 K V..2 U.4 H.6 K.8 15
120
110
100
90
80
70
60
50
40
30
20
10
1 1"Fe ln.pl "Mn U ^ \ | | _
/ X
//
/5 6 7 8 9 10 11 12 13 V, 15 16 17 18 19 20
ElMeV)
FIG. 14. ENDF/B-IVand ENDF/B-V curves compared with other recent evaluations andmeasurements.
toMRT6431 CROSS-SECTIONS 26-FE-56
60O-a
26-FE-56
3 -
gCD
2
o>o>(nu>^inai ( j tu iui i j i ik .&. twA^^«&i^uuua}<*)uucj<JuKitofoufOroroK>-*->-* ->-* - ' ->- ' - *oooooaoooM —CQCB^OCfl A<OK> —CDCD^Ocn<0WOO<0C0^O<fl^Q —OCDCO^Oin AK>—©CO^OCfl AC^W —oC0*»iO»yi ACJW —OCO —COU1U1U1CT1.£K*)K> —<0-»JCIirOOO)COtO©0-» -"-*:-»©OCOCO-JOinCOK>OCOOCOOCoen-* —-» —— O<0CDC0-JO ACO — OX»IO-0»JOO- a)-JOJO>roai<J>C*)a)OCDCJ(JlfOOO WfOO*J<*lCKJ)tO-»4 A<DUUUOO>tO-'-'(0(B^AOUlO)oM-*0<>>JU->JOrnrnrnrnTnrnmfTiTnfTi iTiiTirnrnrnrnmmrTirTi-fnrnrnrnTninrn rnTnm TOTOTTI mmnirnmrnmrnrn rnmrn rnrnrnpifflfflnimmmrn
A CO CO-CO CO K) fOK> t o fO tO—* — — — — — — —<£>CDCDCD—J
300OOOOOOOOOOOTi 0*0) d O) Ol O) O) O Ol O10)'
J — — ™»—. — — — — — — <0 CO CO
OOC*)NJ A<0C0fO<0C0C<OC0tniDO OC— ^ - " O A N U A £h<0C0fO—UllOCOOtO -C«CDO —CO —
WOC0C0JC0l0O W A < 0 ^ 0COCO —CO-^CJtDCDO30)0 010
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D01LTlJCI~J010tnNKJl»0NJCno-J<»OCPi*<JO*K0~J — 0>CJT^ TO TO TO?n TO TO HITT I m TO ni^n TO n i TO TO m JTI TO:TO TO rnTO"TO TO TO f
D-Jo)uoo(ocsa>^->MO)0)a3a9-jaiuiJUtoOO-JUta>CJ10D^0100 A-4C*CJO<J1—*n TO TOTH TO TO TO-m rn TOPI rn^n TOTTI TO TO TOI^
O O O O O O O O O O O O O O O) 0)0)0)0)0)0^0) O) 0)0)0) O)O)O)0)
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O — O CO -0 JO
Mauouaoico£<nu^U(0^uO00>-»—JOfOO-JdCBW^ Ayi-J<DO)aiMCa-*roO)0 A C J C D K J Q J U C O C D O O O C JrnTOrriTTi(THTiTOm TOrnrnmmrnmirn TOTOrnTOTOmTOTnrnrnniTTirniTirnTTimTO mTOmi i i i i i i i i t i i i i i i i i i i i i i • i i i i i i i i i i t i i i i i i i i i. i i i i i i i : i i i i i
OOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOin en ui en oi oioim oi m m yi ui en at en oo)cn o OOJO 01 o 0)0)0)ooo>«» o ciowioomfl ioioioMJioi^N-j- j-JS'j- j 'JS
O O O O D D C C C
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couioicoo-»w—'Cotocoro-J ^cotoo JkKj-co-JXkou>-COCDfO AOQjCJd-JOOCIiyKOWMWtJtCJ AO<Jl-"J0»rnmfTiTTim ni rnfn TO TO m TO TO m firm TO TO rn'Cnmrnrn TO
oo) CO CD -^ —* en COnrnfTjrnfTfntT
oOI (O O A CO CD J (O J — O COtD 4 O OHJ J O) IOO O) i i K3 O J O1O W O M U M CO CO J U O ) J CO CH O) CO CD en CO O OI I I I I I I 1 I I t 1 I t I : I I t I I t I I : I I I I t I I I I I I I I I t I I I I I 1 1 I I 1 1 I : I I I I IOOOOOOOOOOOOO OOOOOOOOOOOO OOOOOOOOOOO 000 -00000000 OOOOO OOOcoco co(o co to co^o co co ^ ^ ^ ^ ^^^ ^ ^ ^ ^ JK ^ ^^^ ^ ^ ^ ^ ^ ^ ^ ^ ^ J^ ^^^^ ^ A ^^cn n n n n t^ en 'j\ en en en^^ n n n n
to —_*— — — — * — — ——_•_._.— — — — _ . _ » —
oooooomooiocoooMuoyooooOOOOOOOOOOOOOOOOOOOOOOOOOo o 00 o o 00 o o 00 o o 00 00 00 o o 00 oTO TO TOfn m rn TO^H TO rri rritn TO TO TOTTI TO TO TOTnTOrnTO^nTO
o o o o o o o u iOOOOOOOCDCO J N O
0 0 o o 0 0 o>co^<ntDornrnTOfnfn^irn rnf^TOTOTO
o ( o W o o c o o ut < 0 O C 0 o —OCOO)CO — CO CO— O COO)-J<o-»en oxo 0 0 tocooooocoo coo
— — — — -»coco-" o — — - * —— co<ococo*jooencn«i
co co -»'ik o> co coo -»o coo o -* -*—• -• o ca>Mco^cocn^Mco^&<7)coN)iooo
J CO - *O I CO M ocoen <o tico i^oeo^^OK)t
«5 - * o co w o ono>CCo«)Ooi
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^^OK)toenoCDCo«OoOOOOOOOCOW(D<OCOOOOOOOOO-M-^OOTO TO^l TO TO f n ^ n TO TO I f l - l l l TO TO
I t i l l 1 1 1 1 I I I I I I I t I I t I I I I I f I I I I 1 I 1 ( f i t IO©OOOOOOOOOOOQOOOOOOOOOOOOOOOOOOOOOOOO
iocococno4ooaocoootooo^O-CO —-J—<00<D-JQ10—03 010 0 0-JA(0-K>-O»J<31ilO0>D>CJOM;-TO"TO TO TO TO;TO TO TOfn TO nTOTH W TO TO^l
I f t I I I I I I I t I I IOOOOOOOCO<OCOWCOtOU
O O O O O O O ©
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fifi!
£9 Z-\
64 BODY
TABLE XII. UNCERTAINTY DATA FORTHE 56Fe(n, p) CROSS-SECTION
Energy range(eV)
3.0E+6 to 5.0E+6
5.0E+6to5.8E+6
5.8E+6 to 6.4E+6
6.4E+6 to 8.5E+6
8.5E+6to 1.1E+7
1.1E+7 to 1.2E+7
1.2E+7to 1.6E+7
1.6E+7 to2.0E+7
Uncertainty
10
8
6
5
4
3
2
3
9. THE I97Au (n, 7) 198Au CROSS-SECTION
Gold has excellent properties as a capture standard. Sample preparation isparticularly easy, since the material is monoisotopic, easy to fabricate and theproduct nucleus has a simple decay scheme. The standard is applied with twodifferent methods, activation and prompt gamma ray detection [ 1, 78]. Theactivation method for gold is well understood; 198Au has a well known decayscheme which makes it very attractive for beta-gamma coincident counting withits inherent self-calibration [28]. The recommended energy range is from 0.2 to3.5MeV[78].
9.1. Status
The ENDF/B-V evaluation was carried out in conjunction with the Standardsand Normalization Subcommittee of CSEWG and its Au Task Force [79].
According to one report on the status of the ENDF/B-V evaluations usingexperimental data published before January 1982: "There seems to be a generalconsensus that the most recent measurements have cross section values lowerthan the ENDF/B-V points for En > 1 MeV. Moreover, Macklin's work suggeststhat this trend continues also at lower energies" [78]. The latter statement issupported by Carlson et al. in their preliminary approach to ENDF/B-VI [42].Blinov et al. consider ENDF/B-V to be too high for energies greater than 2 MeV[80]. Tolstikov considers ENDF/B-V "slightly overestimated" for the same energyregion [81 ].
250
200
150
100 •
50
{1\
Y\
\i\
XV
ENDF/B-V
• Andersson
w* Yamamuro
K Hussdin
• July
o Ma<klin
A Chen Ying
Rels
185,86]
1671
(881
1891
1901
ISM
>s
0.50 100 1.50 2.00 2.50 3 00
£„ [MeV|
FIG. 16. Plots ofENDF/B-V versus recent data of other evaluations and measurements.
350
O\
MflT 1379 CROSS-SECTIONS 79-RU-197
8.o
79-RU-I97
79-AU-197ENERGY
(eV
1.9900E2.QQ0QE2.2000E2.3000E2.4000E2.7000E2.8000E2.9000E3.0000E3.1000E3.2000E3.3000E
)
050505050505050505050505
(N,GAMMA)SIGMA
Ib)
2.4420E-012.575QE-Q12.4500E-012.4000E-012.3400E-012,1900E-012.1480E-012.1000E-O12.0650E-012,0100E-Q11.9500E-011.9100E-01
ENERGYlev)
3.4000E3,600053.9000E4.1000E4.2000E
..4.4000E.4.8000E4.9OOOE5.0000E
514000E6.5000E
050505050505050505Q50505
SIGMAIb)
1 .8600E-011,7500E-Q11 .6300E-011.5600E-011 .5280E-011.4700E-011 .3800E-011.3600E-011 .3460E-011.3.000E-Q11 .2600E-011.0800E-01
ENERGY(eV)
7.0000E...7....5000E
8.0000E8.5000E9.0000E1.0000E1.1000E1.2000E1.3000EL4QQQE1.5000E1.5500E
05Q5050505
.06060606.060606
SIGMA(b)
1 .0100E-019,52QQE-Q2.9.0800E-028.7200E-028.5500E-028,30QQE-027.9200E-027.6000E-027.3500E-027..20Q0E-Q27. 1500E-027.1000E-02
ENERGYlev]
1.7000E. ...1...8QQQE..
2.0000E2.2000E2.4000E2.5000E2.6000E2.7000E2.8000E2.90QQE3.0000E3.5000E
1
060.606060606060606
. 0 6 .0606
MAT 1379
SIGMAIb)
6.5000E-026.15Q0E-Q25.4000E-024.6000E-024.0000E-023,75Q0E-023.4200E-023.2000E-022.9500E-022,750QE-022.6000E-022.0500E-02
> •
7*
1to
FIG. I 7. The mAu(n, y) cross-seccion (ENDF/B-V, Standards File).
68 BODY
TABLE XIII. UNCERTAINTY DATA FOR THE 197Au(n, 7) CROSS-SECTION[78]
Energy range(eV)
2.0E 02to5.0E
5.0E 02to6.0E
6.0E 02 to l.OE
l.OE 03to2.5E
2.5E 03to3.5E
+ 1.000
+0.040
+0.040
+0.000
+0.000
02
02
03
03
03
+ 1.000
+0.060
+0.000
+0.000
Correlation matrix
+ 1.000
+0.190
+0.000
Uncertainty(%)
6.1
4.1
4.1
20.0
20.0
+ 1.000
+0.960 +1.000
For the energy region below 1.15 MeV, Davletshin et al. published recentlyre-evaluated experimental data [82]. The original data of the same authors weredifferent from ENDF/B-V by 16% maximally [78]. However, the former datahave now been corrected for neutron scattering and they fit well to ENDF/B-V.
An evaluation by Chen Ying et al. yielded results above ENDF/B-V forenergies E n < 2 MeV(by 7% maximally) and very slightly below that for energies from2.5 to 3.5 MeV [83, 84]. According to Carlson et al., who have published prelimi-nary results for ENDF/B-VI, the new evaluation "is very similar to that ofENDF/B-V. There are changes of 5-6% in the energy range from 200 to 270 keVcompared to ENDF/B-V as a result of the inclusion of data... which show structuredue to competition with inelastic scattering" (page 81 of Ref. [42]).
The most recent data are plotted with the ENDF/B-V curve in Fig. 16. Theagreement can be considered to be good for the energy region from 1.95 to 2.55 MeV,but otherwise ENDF/B-V is a little higher than the experiments. Anderssonet al. present a slightly corrected version of the data set presented in Ref. [85],though the differences between the two data sets remain within the given errorsin every case [86]. According to the results of Hussain and Hunt, the discrepancyis not as high as previously suspected for the En > 2.5 MeV region [88]. In general,it is desirable to have more (activation-type) measurements available for analysis.
PART 1-2 69
2100 •
2000 -
1900 -
1800 -
1700 -
_
£ 1600 •
0
1500 •
1100 •
1300 •
1200 •
1100 -
1000
X
O
D
A
•
0M
•
X•
\
E.A.Zhagrov et al.
M. Cance and G. Grenier
OA Wasson et at.
Al-walled iycollimator,
Brass-walled '
Li Jingwen et al.
M. Mahdavi el al.
V.N Oushm et al.
R Aril el al.
Yan Wuguang el al.
A.O. Carlson el al.
ENOFxB-v evaluation
\
\ ,
2150 •
2100 •
2050 •
2000 •
Q.A. Wasson el al.
14.0
96!
971
981
99J
1100]
11011
1021
11031
11041
1105.131
JI
r
14.2
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] T
i nK.4 14.6 14.8 150 |
1
rk \[\J
V1 1 r-r-
0.1 0.2 OS 1 2 5 10
E, (HeV)
FIG. 18. Post-1980 measurements of the 23S U(n, fj cross-section plotted alongside theENDF/B-V evaluation.
MflT 1395 CROSS-SECTIONS 92-U -235
'. 2 .0
1.8
. 1 . 6
. 1.1
1.2
8.a
10'92-U -235
1 92-U -235 FISSION MAT 1395
ENERGY(eV)
9 .9300E9.9900E1.OOOOE1... 2000E1 .4000E1.6000E2.OOOOE2,200082.4000E2.6000E2.8000E4.25QQE4.7500E5.4000E6.OOOOE7.OOOOE7.8000E8.3000E8.5000E9.0Q00E
0404050505050505050505050505050505050505
SIGMA(b)
.6172E
.5992E1 .5810E
.5200E
.4760E
.4400E
.377 0E
.3430E1 .314OE
.2910E
.2720E
.1.9.6 OE
.1740E1.1570E1.1450E1.1370E
.1370E
.1420E
.1470E
.J680E
ENERGY(eV)
00 9.6000E00 9.8000E0000000000OQ00
!.OOOOE.05Q0E.1500E-2500E.4000E,70QQE.
1.8000E00 2.OOOOE00 2.1000E00 . .2.30Q0E00 2.8000E00 3.OOOOE00 3.8000E00 4.O0Q0E00 4 .4000E00 5.OOOOE00 5.2000E00
05050606060606060606060606060606060606
SIGMA(b)
1.2070E1.2170E1.2200E1..2150E.1 .2160E1.2230E1 .2390E1,278QE1.2880E1.2980E1.297 0E1.286QE1.24 00E1.2190E1 .1480E1.1320E1.1200E1.0640E1.0520S
000000OQ000000QQ000000OQ00OU00OQ.000000
ENERGY(eV)
5.3000E5.5000E5.6400E5.7000E5.8000E5.9000E6.OOOOE6.2QQ0E6.4C00E6.5000E6.7000E
.7..Q.0Q0E7.2500E7.5000E7.7500E
.8..OOOOE8.2500E8.5000E9.5000E
0606060.6...060606O.6....060606Q606060606....060606
SIGMA(b)
.d480EI .047 0E1 .051CEI.Q550E.0660E
I.0830E1 .1120E
.2Q70E1 .3060EI .364 0EI.4560EI....553.0E..1 .6500E1.7190EI.7630E1 .7820E.
.7840E
.7820E
.7620E
do0000OQ00000000000000QQ000000QQ000000
ENERGYleV)
i.05ddE1.1000E1.1500E1,20Q0E1 .2200E1.3000E1 .3500E
....1...4.Q.QDE...1 .4500E1.5000E1.5500E1..6QQQE.1 .6500E1.7000E1 .7500E.1. 8QQ0E1 .8500E1 .9500E2.OOOOE
0707070707070707....;07 :
SIGMAIb
.7380E1 .7320E1 .732 0EI.7480E1 .7710E1 .9150E1 .9980Ei , 068 OE2.0990E
07 2 .1030E07 2 .0930E07....2....Q6.8QE.07 :070707....0707
2.0360EI.9860EI.9600EV.9390E
.9450E
.9900E07 2 .0240E
)
do0000OQ000000.00000000.0000000000000000
*v
f»
1
FIG. 19. The 2X U(n, f) fission cross-section (ENDF/B- V, Standards File).
72 BODY
TABLE XIV. UNCERTAINTY DATA FOR THE 235U FISSION CROSS-SECTION[HO]
ENERGY RANGE UNCERTAINTY (PER CENT)
1001502004001241015
IceVfceVkeVkeVMeVKeVMeVMeVMeV
TOTOTOTOTOTOTOTOTO
150200400
124101520
keVkeVkeVMeVMeVMeVMeVMeVMeV
4.03.03.03.52.53.03.54.06.0
CORRELATION MATRIX
+1.00+0.60+0.25+0.35+0.07+0.05+0.00+0.00+0.00
+ 1.00+0.60+0.50+0.10+0.10+0.00+0.00+0.00
+1.00+0.60+0.15+0.15+0.00+0.00+0.00
+1.00+0.30+0.25+0.05+0.00+0.00
+1.00+0.40+0.30+0.05+0.03
+1.+0.+0.+0.
00402520
+1+0+0
.00
.45
.40+ 1.00+ 0.80 + 1.00
Another matter of interest is what uncertainties could be ascribed toENDF/B-V. Originally, in 1982, values of 6.1% for 0.2 to 0.5 MeV, 4.1% for0.5 to 1.0 MeV and 20.0% for 1.0 to 3.5 MeV were given [79]. Since then,Ryves, in a very detailed investigation using data published before 1983, hasproposed the following uncertainties for ENDF/B-V: 8% below 2 MeV and 4%for 2 to 3.5 MeV [91]. It should be mentioned that at the 1984 IAEA-OECD/NEANDC Advisory Group Meeting in Geel, the usefulness of the gold capturestandard above 1 MeV was questioned because of the small cross-section andbecause of background problems [11].
Finally, it should be noted that recently a deformed optical model andHauser-Feshbach calculation, together with gamma-ray strength function formu-lations have been found to describe well the n+197Au cross-sections for En =0.01 -20 MeV, as well as neutron emission spectra from 14 MeV neutron reactions [92].Figure 17 and Table XIII detail the 197Au(n, 7) cross-section.
PART 1-2 73
10. THE 235 U (n, f) CROSS-SECTION
The 235U(n, f) cross-section is considered to be a standard at thermal andin the energy region from 0.1 to 20 MeV. Detectors which have been employedto implement this cross-section are basically of two types. Either the very ener-getic fission fragments or fission neutrons are counted. Fission fragment detectionis performed with gaseous ionization chambers, scintillation chambers, solid statedetectors and track-etch film techniques. Fission neutron detection is usuallyaccomplished by using large, high efficiency neutron detectors [1 ].
10.1. Status
The ENDF/B-V file was derived from the evaluation by Poenitz [93] usingpre-1978 data. Below 1 MeV the ENDF/B-IV, ENDF/B-V and the Sowerby et al.[94] evaluations agree reasonably well, the largest differences being less than 2%.From 1 to 1.5 MeV, the ENDF/B-V evaluation is lower than ENDF/B-IV, thoughthe Sowerby et al. evaluation is even lower than ENDF/B-V. Above 13 MeV,ENDF/B-V is significantly lower than both the ENDF/B-IV and the Sowerby et al.evaluations, according to Carlson [ 1 ]. Otherwise, ENDF/B-V, JENDL-2, ENDL-82and KEDAK-4 all agree with each other within 4% over the relevant MeV region [95].
The results of measurements reported since 1980 are plotted in Fig. 18along with the ENDF/B-V evaluation. It is apparent that below about 2 MeV,the majority of the data lie below the ENDF/B-V values. (Sowerby and Patrickarrived at the same conclusion earlier using nearly the same data [106].) Abovethis energy the results are in reasonable agreement with ENDF/B-V (see alsoRef. [107]).
According to a preliminary evaluation of ENDF/B-VI, it is approximatelythe same above 4 MeV, ~ 1-2% lower from 1-4 MeV and ~ 2% lower from 0.1-1 MeVcompared with ENDF/B-V. An indication of the reduction in the evaluatedcross-section is given by the calculated average 235U(n, f) cross-section in a 252Cfspontaneous fission neutron spectrum. This quantity is ~ 1.5% lower for the newevaluation as compared with ENDF/B-V [42]. Specifically, the value of (a),that is the 2s2Cf spectrum averaged neutron cross-section of 23SU(n, f), is1210 ± 14 mb (recommended value), while this cross-section is 1236 mb (seePart 2-4) if calculated using ENDF/B-V for 23SU (n, f). The (a) valuecalculated using ENDF/B-VI is smaller. Therefore, one can say, on the basis ofthe experimental values of <<7>, that version VI of ENDF/B is preferable, orthat a reduction of the ENDF/B-V values is justified in some average sense.However, it is a general feeling that the uncertainties contained in the ENDF/B-Vfile [93] are more or less correct, except for data at around 14 MeV where thecross-section is known to be < 1% [1, 106, 108, 109,80]. Figure 19 andTable XIV detail the 23SU(n, f) cross-section.
HOT 6398 CROSS-SECTIONS 92-U -238
i 3
s.
92 -U -238
92-U -238
ENERGY(eV)
5.OOOOE5.5000E5..80.QOE.5 9OOOE6.OOOOE6.2000E6.4000E6.5000E6.6000E6.8000E7.OOOOE7.5000E7.8000E8.OOOOE8.5000E8.8000E9.OOOOE9.2000E9.5000E9.7000E
05050505050505050505.05050505050505050505
FISSION
SIGMA(bl
3.7850E-046.3300E-046,9460ErQ47.6300E-048.2710E-049.3280E-041,134 0E-031 .2460E-031.3010E-031.5830E-03),7260ErQ32.5880E-033.5980E-034.4950E-037.2080E-031.0830E-021.3700E-021 .5580E-021.6630E-021 .5910E-02
ENERGY(eV)
1.OOOOE1.0200EI....0.3Q0E.....0500E.0800E
1 . 1000E1,1300E
. 1400E1 .1500E1.1700E... 2QQ0E...2300E
1 .24 00E.2500E•2800E. 3000E
I.3500E1 .4000E1 .4500E1 .4800E
06060606060606060606Q6060606060606060606
SIGMA(b)
1 .7120E-021.6650E-021,7Q2QE-02.1 .9550E-022.4800E-022.8850E-023.3890E-023.5640E-023.7630E-024.0470E-02
.4,2320E-024. 1580E-024.2970E-024.5810E-025,9160E-027.059OE-021.1250E-011.8890E-012.8380E-013.2990E-01
ENERGY(eV)
1 .5000E1.5500E1.6000E...1.8000E1.900OE2.OOOOE2,1000E2.2000E2.5020E2.8000E
...3..,.0QQ0E...3.1OOOE3.5000E3.7000E4,2000E4 . 5'00'OE5.OOOOE5.5000E6,OOOOE6.2000E
060606060606Ofi06060606060606060606060606
SIGMA(b)
3.4670E-013.8020E-014,0630E-01 .4.8910E-015. 1890E-015.3370E-015,3880E-015.4170E-015.3895E-015.3120E-015,226QE-01..5.2280E-015.3270E-015.4390E-015.4780E-015.4920E-015.3340E-015.4740E-016.126QE-Q16.8640E-01
ENERGY(eV)
6.4000E6.5000E6.6000E6.8000E7.OOOOE7.5000E9.OOOOE1.OOOOE1.1000E1.1500E
. 1,2QQQE.1.3000E1.3500E1.4500E1.5000E1 .6000E1.7000E1 .8000E
. 1.90QOE2 . OOOOE
MAT 6398
SIGMA(b)
06 7.7360E-0106 8.0910E-0106 8.3980E-0106 8.9350E-0106 9.2180E-0106 9.8710E-0106 9.9840E-0107 9.8200E-0107 9.8670E-0107 9.8730E-0107 9,8480E-Q10707070707070707..07
I.0200E 00I.0670E 001. 1720E 00.2160E 00
I.2720E 00I.2740E 001.2880E 00I..3360E OQ1.4180E 00
"0
90
FIG. 20. The 23tU(n, f) fission cross-section (ENDF/B-V, Mod. 2, Dosimetry Library).
76 BODY
TABLE XV. UNCERTAINTY DATA FORTHE 2 3 8U FISSION CROSS-SECTION [111]
Energy(MeV)
0.3
0.4
0.5
0.6
0.7
0.8
0.9
1.0
1.2
1.4
1.6
2.0
2.5
3.0
4.0
5.0
6.0
8.0
10.0
12.0
14.0
20.0
Uncertainty(%)
8.9
10.0
12.0
11.3
11.0
8.3
7.7
7.9
6.1
7.4
1.3
1.3
2.9
2.4
2.3
2.6
3.9
3.2
2.9
3.7
4.3
8.4
11. THE 238U (n, f) CROSS-SECTION
This cross-section is a useful reference standard in fast-neutron flux determi-nations, relative fission cross-section measurements and dosimetry applications.The threshold nature of the process makes it reasonably free of thermal back-ground problems [111]. Detectors which have been employed to implementthis cross-section are basically of two types. Either the very energetic fission
PART 1-2 77
fragments or fission neutrons are counted. Fission fragment detection is performedwith gaseous ionization chambers, scintillation chambers, solid state detectorsand track-etch film techniques. Fission neutron detection is usually accomplishedby using large, high efficiency neutron detectors [24, 1]. Originally, these cross-sections were recommended as standards between threshold and 20 MeV [24],but nowadays for energies below 2 MeV they are not recommended.
11.1. Status
The ENDF/B-V evaluation was carried out at the Argonne National Labora-tory by a task force [112]. Most of the experimental information was availablein the form of fission cross-section ratios relative to the 23SU fission cross-section,while a smaller fraction came from measurements employing absolute flux determi-nations. The two sources of information were separately evaluated in order to obtainthe cross-sections from the ratio and absolute measured values; the two resultswere combined to obtain the final 238U(n, f) cross-section values [111].
A comparison of ENDF/B-V with other files (such as JENDL-2, KEDAK-4,ENDL-82 and UKNDL-1981) has been done by Kanda and Uenohara, whoconcluded that the differences between the data sets were below ±6% whenUKNDL-1981 was included, and below ±4% when it was excluded between2 and 15 MeV [95]. The differences below 2 MeV were found to be very great(20% or more). It is worthwhile taking note here of Smith's conclusion concerningthe applicability of the 238U(n, f) cross-section, that it is not useful as a standardbelow 2 MeV [28].
Kanda made an extensive comparison with new experimental data reportedsince 1977. He concluded that it was not necessary to revise the earlier conclusions.In the region from threshold to 10 MeV, the recommended cross-sections were asaccurate as a few per cent, while above 10 MeV, the difference between the experi-mental data was as large as 10% of the values [113]. It should be mentioned thatthere are some new measurements currently in progress that will considerablyimprove the situation at higher energies [28]. Finally, 238U(n, f) values will beforthcoming from the standards evaluation process for ENDF/B-VI, as describedin the Introduction. Figure 20 and Table XV detail the 238U(n, 0 cross-section.
ACKNOWLEDGEMENTS
The assistance of A.D. Carlson, H. Conde, A.B. Smith, K. Okamoto andD.E. Cullen in the preparation of this chapter is acknowledged.
78 BODY
REFERENCES
[1] CARLSON, A.D., Prog. Nucl. Energy 13(1984)79.[2] POENITZ, W.P., WHALEN, J.F., Nucl. Phys. A383 (1982) 224.[3] DIAS, M.D., et al., in Nuclear Data for Science and Technology (Proc. Int. Conf. Antwerp,
1982) (BOCKHOFF, K.H., Ed.), Reidel, Dordrecht (1983) 875.[4] GAMMEL, J.L., in Fast Neutron Physics (MARION, J.B., FOWLER, J.L., Eds), Wiley-
Interscience, New York (1963).[5] HOPKINS, J.C., BREIT, G., Nucl. Data A9 (1971) 137.[6] STEWART, L., et al., Los Alamos Scientific Lab., NM, Rep. LA-4574 (1971).[7] STEWART, L., LABAUVE, R.J., YOUNG, P.G., in Brookhaven National Lab., Upton,
NY, Rep. BNL-NCS-51619 (1982) 3.[8] LOMON, E., WILSON, R., Phys. Rev. C 9(1974) 1329.[9] DILG, W., Phys. Rev. C 11 (1975) 103.
[10] UTTLEY, C.A., "The H(n, n) cross section", Nuclear Data Standards for NuclearMeasurements, Technical Reports Series No. 227, IAEA, Vienna (1983) 3.
[11] CONDE, H., private communication to K. Okamoto, 1985.[12] TORNOW, W., et al., Nucl. Phys. A340 (1980) 34.[13] CARLSON, A.D., private communication to K. Okamoto, 1985.[14] STEWART, L., in Brookhaven National Lab., Upton, NY, Rep. BNL-NCS-51619
(1982) 19.[15] HALE, G.M., STEWART, L., YOUNG, P.G., Los Alamos Scientific Lab., NM, Rep.
LA-6518-MS(1976).[16] ALS-NIELSEN, J., DIETRICH, O., Phys. Rev. 133B (1964) 925.[17] GIBBONS, J.H., MACKLIN, R.L., Phys. Rev. 114 (1959) 571.[18] MACKLIN, R.L., GIBBONS, J.H., in Study of Nuclear Structures with Neutrons (Proc.
Int. Conf. Antwerp, 1965), North-Holland, Amsterdam (1966) 498.[19] WASSON, O.A., in Nuclear Cross Sections for Technology (Proc. Int. Conf. Knoxville,
TN, 1979), US National Bureau of Standards Special Publication 594-GA1, US Govern-ment Printing Office, Washington, DC (1980) 720.
[20] BORZAKOV, S.B., et al., Yad. Fiz. 35 (1982) 532; Sov. J. Nucl. Phys. (Engl. Transl.)35 3 (1982)307.
[21] BOWMAN, CD., et al., in Nuclear Cross Sections for Technology (Proc. Int. Conf.Knoxville, TN, 1979), US National Bureau of Standards Special Publication 594-AC6,US Government Printing Office, Washington, DC (1980) 97.
[22] LOPEZ, W.M., et al., Gulf General Atomic Co., San Diego, Rep. GA-8835 (1968) 59.[23] HALE, G.M., Brookhaven National Lab., Upton, NY, Rep. BNL-NCS-51363, Vol. 2
(1981)509.[24] DERUYTTER, A. J., "Requirements for nuclear standard reference data from the users'
point of view", Nuclear Standard Reference Data, IAEA-TECDOC-335, IAEA, Vienna(1985)65.
[25] LAMAZE, G.P., in Neutron Standards and Applications (Proc. Int. Symp. Gaithersburg,MD, 1977), US National Bureau of Standards Special Publication 493, US GovernmentPrinting Office, Washington, DC (1977) 37.
[26] WESTON, L.W., ibid., p. 43.[27] HARVEY, J.A., HILL, N.W., Nucl. Instrum. Methods 162(1979) 507.[28] SMITH, A.B., private communication to K. Okamoto, 1983, 1985.[29] FARRAR, H., IV, et al., Nucl. Technol. 25 (1975) 305.[30] FARRAR, H., IV, et al., Brookhaven National Lab., Upton, NY, Rep. BNL-NCS-50681
(1977) 175.
PART 1-2 79
[31] KNEFF, D.W., et al., Brookhaven National Lab., Upton, NY, Rep. BNL-NCS-51245(1980)289.
[32] WU, C.H., WOELFLE, R., QAIM, S.M., Nucl. Phys. A329 (1979) 63.[33] WU, C.H., WOELFLE, R., QAIM, S.M., Nucl. Phys. A410 (1983) 421.[34] HALE, G.M., STEWART, L., YOUNG, P.G., in Brookhaven National Lab., Upton, NY,
Rep. BNL-NCS-51619O982) 25.[35] DIMENT, K.M., UTTLEY, C.A., UKAEA Atomic Energy Research Establishment,
Harwell, Rep. AERE-PR/NP 15,16 (1969).[36] POENITZ, W.P., "The data for the neutron interactions with 6Li and 10B", Nuclear
Standard Reference Data, IAEA-TECDOC-335, IAEA, Vienna (1985) 112.[37] HALE, G.M., "The 6Li(n, t)4He cross section", Nuclear Data Standards for Nuclear
Measurements, Technical Reports Series No. 227, IAEA, Vienna (1983) 11.[38] GAYTHER, D.B., UKAEA Atomic Energy Research Establishment, Harwell, Rep.
AERE-R-8856U977).[39] RENNER, C, et al., Bull. Am. Phys. Soc. 23 (1978) 526.[40] ENGDAHL, F.C., et al., Nucl. Sci. Eng. 78 (1981) 44.[41] SHIBATA, K., Japan Atomic Energy Research Institute, Tokyo, Rep. JAERI-M-84-198
(1984).[42] CARLSON, A.D., et al., "The neutron cross-section standards evaluations for ENDF/B-VI",
Nuclear Standard Reference Data, IAEA-TECDOC-335, IAEA, Vienna (1985) 77.[43] CARLSON, A.D., in Neutron Standards and Applications (Proc. Int. Symp. Gaithersburg,
MD, 1977), US National Bureau of Standards Special Publication 493, US GovernmentPrinting Office, Washington, DC (1977) 85.
[44] HALE, G.M., STEWART, L., YOUNG, P.G., in Brookhaven National Lab., Upton, NY,Rep. BNL-NCS-51619 (1982) 31.
[45] YOUNG, P.G., The 10B(n, a)7Li Reaction, Los Alamos National Lab., NM, Rep.LA-UR-84-2083U984).
[46] QI, Huiquan, et al., in IAEA/International Nuclear Data Committee, Vienna, Rep.INDC(CPR)-001/L(1985) 14.
[47] WATTECAMPS, E., "The 10B(n, a) cross section", Nuclear Data Standards for NuclearMeasurements, Technical Reports Series No. 227, IAEA, Vienna (1983) 19.
[48] WRENDA 83/84 (PIKSAIKIN, V., Ed.), IAEA/International Nuclear Data Committee,Vienna, Rep. INDC(SEC)-88/URSF (1983).
[49] SMITH, A.B., et al., in Nuclear Data for Science and Technology (Proc. Int. Conf. Antwerp,1982) (BOCKHOFF, K.H., Ed.), Reidel, Dordrecht (1983) 39.
[50] SMITH, A.B., "The C(n, n) cross section", Nuclear Data Standards for Nuclear Measure-ments, Technical Reports Series No. 227, IAEA, Vienna (1983) 25.
[51] FU, C.Y., PEREY, F.G., in Brookhaven National Laboratory, Upton, NY, Rep.BNL-NCS-51619(1982)35.
[52] HOLT, R., SMITH, A., WHALEN, J., Argonne National Lab., IL, Rep. ANL/NDM-43(1978).
[53] SHIBATA, K., Japan Atomic Energy Research Institute, Tokyo, Rep. JAERI-M-83-221(1983).
[54] VONACH, H., "The 27Al(n, a) cross section", Nuclear Data Standards for NuclearMeasurements, Technical Reports Series No. 227, IAEA, Vienna (1983) 59.
[55] HALE, G.M., STEWART, L., YOUNG, P.G., Los Alamos Scientific Lab., NM, Rep.LA-8036-PR(1979)13.
[56] TAGESEN, S., VONACH, H., Physics Data 13-l,Fachinformationszentrum, Karlsruhe(1981).
80 BODY
[57] CONDE, H., "INDC/NEANDC standards file, status report", Nuclear Standard ReferenceData, IAEA-TECDOC-335, IAEA, Vienna (1985) 84.
[58] EVAIN, B.P., SMITH, D.L., LUCCHESE, P., Argonne National Lab., IL, Rep. ANL/NDM-89(1985).
[59] WINKLER, G., RYVES, T.B., Ann. Nucl. Energy 10 (1983) 601.[60] RYVES, T.B., "A simultaneous evaluation of some important cross-sections at 14.70 MeV,
Nuclear Standard Reference Data, IAEA-TECDOC-335, IAEA, Vienna (1985)[61] KORNILOV, N.V., et al., "Evaluation of the 27Al(n, a) reaction cross-section in energy
range 5.5 MeV-20 MeV", Nuclear Standard Reference Data, IAEA-TECDOC-335, IAEA,Vienna (1985) 135.
[62] LI, Jizhou, in IAEA/International Nuclear Data Committee, Vienna, Rep. INDC(CPR)-001/L(1985).
[63] ANTONOV,A.,etal.,Bulg. J. Phys. 10(1983)601.[64] GARLEA, I., et al., IAEA/International Nuclear Data Committee, Vienna, Rep.
INDC(ROMH5/GI(1983).[65] ENZ, W., et al., OECD/NEA Nuclear Data Committee, Paris, Rep. NEANDC-(E)-242-U
(1983), Vol. 5, p. 57.[66] KUDO, K., et al., "Cross-section measurements of S6Fe (n, p)S6Mn and 27Al(n, a)24Na
between 14.0 and 19.9 MeV", Nuclear Standard Reference Data, IAEA-TECDOC-335,IAEA, Vienna (1985) 449.
[67] FU, C.Y., ORNL, Oak Ridge National Lab., TN, ENDF/B-V Dosimetry File (1978)Mat. 6431.
[68] DUDEY, N.D., KENNERLEY, R., in Brookhaven National Lab., Upton, NY, Rep.BNL-NCS-50446(1975)80.
[69] SMITH, D.L., MEADOWS, J.W., Nucl. Sci. Eng. 58 (1975) 314.[70] FU, C.Y., et al., in Nuclear Cross Sections for Technology (Proc. Int. Conf. Knoxville,
TN, 1979), US National Bureau of Standards Special Publication 594-AB7, US Govern-ment Printing Office, Washington, DC (1980) 63.
[71] LU, Hanlin, et al., At. Energy Sci. Technol. 2(1975) 113.[72] SHARMA, D., et al., in Nuclear Physics and Solid State Physics (Proc. Int. Symp.
Bombay, 1978), Vol. 2, Department of Atomic Energy, Bombay (1979) 349.[73] RYVES, T.B.,etal.,Metrologia 14(1978) 127.[74] PEPELNIK, R., et al., OECD/NEA Nuclear Data Committee, Paris, Rep. NEANDC-(E)-252U
(1984)30.[75] RAICS, P., et al., in Neutron Physics (Proc. 5th AU-Union Conf. Kiev, 1980), Vol. 1,
TsNII atominform, Moscow (1980) 242.[76] LU, Hanlin, Chin. J. Phys. 3(1981) 289.[77] SIMONS, R.L., McELROY, W.N., Battelle Pacific Northwest Labs., Richland, WA, Rep.
BNWL-1312O970).[78] CORVI, F., "The "7Au(n, 7) cross section", Nuclear Data Standards for Nuclear
Measurements, Technical Reports Series No. 227, IAEA, Vienna (1983) 33.[79] MUGHABGHAB, S.F., in Brookhaven National Lab., Upton, NY, Rep. BNL-NCS-51619
(1982)47.[80] BLINOV, M.V., et al., "IAEA standards file: some comments and recommendations",
Nuclear Standard Reference Data, IAEA-TECDOC-335, IAEA, Vienna (1985) 89.[81] TOLSTIKOV, V.A., "Comments to the evaluation of fast neutron radiation capture
by 197Au given in the book of standard nuclear data", Nuclear Standard ReferenceData, IAEA-TECDOC-335, IAEA, Vienna (1985) 147.
[82] DAVLETSHIN, A.N., et al., in Nuclear Physics (Proc. 6th All-Union Conf. Kiev, 1983),Neutronnaya Fiz. 3 (1984) 211 (in Russian).
PART 1-2 81
[83] CHEN, Ying, et al., in Nuclear Data for Science and Technology (Proc. Int. Conf.Antwerp, 1982) (BOCKHOFF, K.H., Ed.), Reidel, Dordrecht (1983) 462.
[84] CHEN, Ying, et al., Chin. J. Phys. 3(1981)52.[85] ANDERSSON, P., ZORRO, R., BERGQVIST, I., "Neutron-capture cross-section
measurements for 197Au and n 5In in the energy region 2.0-7.7 MeV using the activationtechnique", Nuclear Standard Reference Data, IAEA-TECDOC-335, IAEA, Vienna(1985) 143.
[86] ANDERSSON, P., et al., Nucl. Phys. A443 (1985) 404.[87] YAMAMURO, N., et al., J. Nucl. Sci. Technol. 20 10(1983)797.[88] HUSSAIN, H.A., HUNT, S.E., Int. J. Appl. Radiat. Isot. 34 (1983) 731.[89] JOLY, S., et al., Nucl. Sci. Eng. 70 (1979) 53.[90] MACKLIN, R.L., Nucl. Sci. Eng. 79 (1981) 265.[91] RYVES, T.B., Argonne National Lab., IL, Rep. ANL-83-4 (1983).[92] YOUNG, P.G., ARTHUR, E.D., in Capture Gamma-Ray Spectroscopy and Related
Topics (Proc. Int. Symp. Knoxville, TN, 1984) (RAMAN, S., Ed.), AIP Conf. Proc.No. 125, American Institute of Physics, New York (1985) 530.
[93] POENITZ, W.P., in Brookhaven National Lab., Upton, NY, Rep. BNL-NCS-51619(1982)59.
[94] SOWERBY, M.G., et al., Ann. Nucl. Sci. Eng. 1 (1974) 409.[95] KANDA, Y., UENOHARA, Y., "Fission ratios involving 238U, 237Np, 239Pu and 235U
fission cross-sections", Nuclear Standard Reference Data, IAEA-TECDOC-335, IAEA,Vienna (1985) 200.
[96] ZHAGROV, E.A., et al., in Neutron Physics (Proc. 5th All-Union Conf. Kiev, 1980),Vol. 3, TsNII atominform, Moscow (1980) 45.
[97] CANCE, M., GRENIER, G., CEA Centre d'Etudes de Bruyeres-le-Chatel, France, Rep.CEA-N-2194 (1981).
[98] WASSON, O.A., et al., Nucl. Sci. Eng. 80 (1982) 282.[99] WASSON, O.A., et al., Nucl. Sci. Eng. 81 (1982) 196.[100] LI, Jingwen, et al., in Nuclear Data for Science and Technology (Proc. Int. Conf. Antwerp,
(1982) ( BOCKHOFF, K.H., Ed.), Reidel, Dordrecht (1983) 55.[101] MAHDAVI, M., et al., ibid., p. 58.[102] DUSHIN, V.M., et al., At. Ehnerg. 55 (1983) 218.[103] ARLT, R., et al., "Absolute measurement of the 23SU fission cross-section at 4.45 MeV
neutron energy using the time-correlated associated particle method (TCAPM)", NuclearStandard Reference Data, IAEA-TECDOC-335, IAEA, Vienna (1985) 174.
[104] YAN, Wuguang, et al., At. Energy Sci. Technol. 2 (1975) 133.[105] CARLSON, A.D., et al., "Absolute measurements of the 23SU(n, f) cross-section for
neutron energies from 0.3 to 3 MeV", Nuclear Standard Reference Data, IAEA-TECDOC-335,IAEA, Vienna (1985) 162.
[106] SOWERBY, M.G., PATRICK, B.H., "Review of recent measurements of the U-235 fissioncross-section and fission fragment angular distribution between 0.1 and 20 MeV", NuclearStandard Reference Data, IAEA-TECDOC-335, IAEA, Vienna (1985) 151.
[107] DIAS, M.S., CARLSON, A.D., JOHNSON, R.G., WASSON, O.A., "Application of thedual thin scintillator neutron flux monitor in a 235U(n, f) cross-section measurement",Nuclear Standard Reference Data, IAEA-TECDOC-335, IAEA, Vienna (1985) 467.
[108] YUAN, Hanrong, IAEA/International Nuclear Data Committee, Vienna, Rep.INDC(CPR)-001/L(1985).
[109] YUAN, Hanrong, "AEP measurements of 23SU(n, f) and 238U(n, f) cross-section",Nuclear Standard Reference Data, IAEA-TECDOC-335, IAEA, Vienna (1985) 167.
82 BODY
[110] YANKOV, G.B., "The 23SU fission cross section", Nuclear Data Standards for NuclearMeasurements, Technical Reports Series No. 227, IAEA, Vienna (1983) 39.
[Ill] SMITH, A.B., "The 238U fission cross section", Nuclear Data Standards for NuclearMeasurements, Technical Reports Series No. 227, IAEA, Vienna (1983) 53.
[112] POENITZ, W.P., et al., Argonne National Lab., IL, Rep. ANL/NDM-32 (1977).[113] KANDA, Y., "The 238U fission cross-section, threshold to 20 MeV", Nuclear Standard
Reference Data, IAEA-TECDOC-335, IAEA, Vienna (1985) 191.
Neutron Source Standards
1-3. PRODUCTION OF MONOENERGETICNEUTRONS BETWEEN 0.1 AND 23 MeVNeutron energies and cross-sections
M. DROSGInstitute for Experimental Physics,University of Vienna,Vienna, Austria
O. SCHWERERNuclear Data Section,Division of Research and Laboratories,International Atomic Energy Agency,Vienna
Abstract
PRODUCTION OF MONOENERGETIC NEUTRONS BETWEEN 0.1 AND 23 MeV: NEUTRONENERGIES AND CROSS-SECTIONS.
The angular dependences of neutron energies and cross-sections are given in the form ofgraphs for neutron production by the 'H(t, n)3He, 'H(?Li, n)7Be, 2H(d, n)3!^, 2H(t, n)*He,'HCp, n)3He, ^ ( d , n)*He and 7Li(p, n) ;Be reactions. In addition, tables with Legendre coefficientsare given which allow the accurate calculation of cross-sections at arbitrary angles and energiesutilizing a short computer code. The same code also calculates, relativistically, neutron energiesand the conversion of angles and cross-sections from the centre of mass to the laboratory system.A discussion of the individual source properties and an intercomparison of the various sourcesare presented to assist in selecting the optimum neutron source for a given experimental situation.
1. INTRODUCTION
Fast monoenergetic neutrons can be produced by two-body nuclear reactionsinduced by projectiles from an accelerator. The target nuclei of the reaction isotopeare situated in the active region of the target assembly. The target structure, whichcontains or supports the active part of the target and usually stops the unusedportion of the beam, may affect the beam characteristics (divergence, energy pro-file) and may contribute neutrons of undesired energy (background). For thesereasons, not only must intrinsic source properties, such as intensity (absolute valueand angular dependence), energy (definition, resolution and angular dependence)and background (contamination by secondary neutrons), be discussed, but also thetechnical realizations of neutron sources.
83
8 4 DROSG and SCHWERER
Not considered here are (p, n) reactions in medium weight nuclei which pro-duce monoenergetic neutrons down to a few keV, e.g. 4sSc(p. n)45Ti. 51V(p, n)s lCrand S7Fe(p. n)S7Co. The properties of these reactions have been collected else-where [1-3]. The reactions that are discussed here are those involving the hydrogenisotopes, as well as the p-7Li reaction and its inverse. The data on the formerreactions are based mostly on previous work [4-8] and, for low energies, on thecompilation of Liskien and Paulsen [9]. The data on the latter reactions are derivedsolely from a compilation by Liskien and Paulsen [10].
A number of graphs provide first information on neutron laboratory pro-duction cross-sections and energies. The ready availability of computers nowadaysmakes a presentation in tabular form unnecessary. The short Fortran IV programgiven in the appendix permits the accurate calculation of these quantities at anyangle and for any energy within the range covered by the tables of the Legendrecoefficients that are included here. Upon request, an even more sophisticatedprogram, which includes the Legendre coefficients needed, can be obtained fromthe Nuclear Data Section (Division of Research and Laboratories) of the IAEA.This latter program was written in Fortran for ready use on PDP-11 computers ofthe Digital Equipment Corporation.
2. SELECTION OF THE APPROPRIATE SOURCE
The suitability of a neutron source for a given experimental problem can onlybe discussed in general terms because of the large variety of different experimentalset-ups. The following discussion should help in selecting the most suitable type ofsource. However, it may not be the one routinely used at any particular installa-tion. If that is the case, then the benefits of switching to a better source mustbe weighed against the effort involved. This discussion is kept at a more generallevel than is actually required for standard neutron activation work. Therefore,for specific applications, some of the following considerations may be disregarded.
It is obvious that the optimum source yields a result that is within the. desireddegree of precision in a minimum amount of time and effort. Whereas the effortdepends strongly on the individual experimental set-up (such as ion sources, theaccelerator, the detecting system, etc.) and, therefore, must be ignored here, the timeelement is strongly correlated to the type of neutron source (its intensity and the back-ground situation). Of course, these two properties also depend on the specificexperimental situation (e.g. maximum beam current, target structure, layout of theexperimental area and type of sample). These influences, however, cannot be dealtwith in a general way and, therefore, must be considered individually. A moredetailed discussion, especially of the monochromaticity of the neutron beam, canbe found elsewhere [3].
PART 1-3 85
2.1. Neutron source intensity
Source intensities should be compared for equal neutron energy spreads in thesample at equal beam currents. (In practice, one would allow for the difference inmaximum beam currents delivered by the machine or allowed by the maximumheat dissipation in the target.)
The neutron energy resolution depends on the effective energy spread of thecharged particle beam in the active volume of the target (accelerator and targetproperties) and on the geometric neutron energy spread (caused by the openingangle of the sample and increased by angular straggling of the charged particlesin the target and any intrinsic divergence of the charged particle beam). Using agas target, the main contributors to the full width at half maximum (FWHM) of theenergy spread for measurements at 0° are the energy straggling in the entrance foiland the energy loss in the active volume. (According to Klein et al. [ 11 ], these twocontributions must be added cubically rather than quadratically.)
En(0°)[MeV]
FIG. 1. Energy dependence of the maximum geometric neutron energy spread at 0°caused bya 5° opening angle of the sample for projectiles with no energy spread. The curves for t-H, p-Tand p-nLi can be approximated by a constant relative energy spread of 1, 0.3 and 0.15%,respectively.
86 DROSG and SCHWERER
oa.
c
O
LLJ
o
CDO
- 7
0.2-
Li-H
p-7Li
H 1—I I I I l-t
En (MeV)
FIG. 2. Energy dependence ofthe specific 0°neutron yield. Except for d-Tand t-D, the thickcurves indicate the monoenergetic range of the reaction in question. The index TT denotes thesecond neutron group at 0° (180° in the centre of mass system).
The finite opening angle of the sample not only further broadens the energyspread, but also results in a shift of the neutron energy to its mean by weightingthe neutron energies with their intensities (the angular dependences of laboratorycross-sections and of the effective solid angles). (However, there is strong angledependence: near 90° this shift will vanish.) Figure 1 gives the difference inneutron energy at 0° and 5° for the reactions considered here. This difference isthe minimum energy spread that can be achieved for an opening angle of thesample of 5° The curves for t-H, p-T and p-7Li are quite linear, corresponding toan energy independent relative energy spread of 1, 0.3 and 0.15%, respectively.There is no simple relation to combine the FWHM geometric energy spread (forneutrons generated in the centre of the target) with the FWHM energy spread at
PART 1-3 87
0° (from the energy loss of the projectile in the target) because the energy depen-dence of the kinematics must not be neglected. It appears that the absolute(additive) contribution from the finite opening angle to the FWHM of the totalenergy spread is minimum if the two spreads discussed before are about equal.Also, for thicker targets the geometric contribution remains small. The beamstraggling [ 11 ] in the foil hardly affects the FWHM of the energy spread or themean neutron energy, but it changes the profile of the energy distribution by pro-ducing a low energy tail.
From all these contributions to the energy resolution, the target thicknessmust (and can easily) be included in a general yield comparison. To first order, boththe yield and the energy spread (caused by the energy loss of the charged particlebeam) are proportional to the target thickness. For the reactions considered here.Fig. 2 presents the specific neutron yield at 0° as a function of the neutron energy,with a target thickness corresponding to a neutron energy spread of 10 keV (assum-ing singly charged incoming particles). Neutron production at 0° is usually pre-ferred because the neutrons are unpolarized and, in general, all properties (aniso-tropies, the energy spread, the signal to background ratio, etc.) are optimum atthis angle. For a larger acceptable neutron energy spread (at higher energies aspread of the order 0.1 MeV is more common), the yield increases in proportionto the spread. If the active region of the target consists not only of the reactionisotope, then the yield is decreased because of the additional energy loss by the othernuclei, e.g. by a factor of 10 when Ti hydrides are used for the hydrogen isotopes[3]. Nevertheless, such solid hydrogen targets can give a better overall performancewhen high energy resolution at lower neutron energies is necessary because theentrance foil of an equivalent gas target would give too much straggling.
The following general features can be seen from Fig. 2. The t-H reaction(:H(t, n)3He) has the highest specific yield, followed by the p-T reaction(3H(p, n)3He). Above 8 MeV, the d-D reaction (2H(d, n)3He) has a marginallyhigher yield (less than 20% higher) than the p-T reaction, while below 0.75 MeV,the p-7Li reaction (7Li(p, n)7Be) has a higher yield than p-T. Finally, the yield ofthe d-T reaction (3H(d, n)4He), even at the resonance, is less (by more than a factorof 100) than that of the t-H reaction, while the t-D reaction (2H(t, n)4He) has ahigher specific yield than the d-T reaction between 15.07 and 17.02 MeV. Onlybelow about 1.7 MeV is the yield of the 7Li-H reaction (1H(7Li, n)7Be) outstanding.However, even in the 'monoenergetic' range, the second line (corresponding to 180°in the centre of mass (cm.) system) is negligible neither in energy nor in intensity.Near 0.6 MeV, the specific neutron yield from this second line is three times that ofp-7Li. In special cases, where a higher energy background line is acceptable, it ispossible to take advantage of this high yield.
The closeness of the d-D and the p-T curves above 8 MeV suggests the need fora more detailed comparison in this energy range. This was done in Table I underthe assumption of identical gas targets (entrance foils of 5.3 mg/cm2 molybdenum)for total energy spreads of 0.1 MeV neutron energy (which includes contributions
0000
TABLE I. YIELD COMPARISON FOR THE SAME TOTAL NEUTRON ENERGY SPREAD (FWHM = 100 keV) ANDSAME POWER (0.2 W) IN A 5.3 mg/cm2 MOLYBDENUM ENTRANCE FOIL OF A GAS TARGET(All energies in MeV)
8 MeV neutrons
p-Td-D
10 MeV neutrons
p-Td-D
E ma
8.9575.115
10.9417.134
AE fb
0.1360.307
0.1180.252
Projectile data
AEgas
0.0400.043
0.0400.043
AEgeo'
0.0120.013
0.0150.017
'max(juA)
1.470.65
1.700.79
AE s t re
0.0510.040
0.052
0.043
AEgas
0.0800.083
0.079
0.082
Neutron data
AEgeo
0.0240.026
0.0300.032
Specificyieldf
8.367.66
10.9
12.5
Flux8
1.00.4
1.50.8
a Energy of accelerated projectile.b Energy loss in entrance foil.c Correction of beam energy to give the correct mean neutron energy with an opening angle of ±5°
Maximum current for a power of 0.2 W dissipated in the entrance foil.e FWHM of energy smearing due to energy straggling.f In units of n s r " ' p C " ' for an energy loss in the gas resulting in a 10 keV energy spread.
o58Ov>
ag.oa7)m
PART 1-3 89
from energy and angular straggling in the entrance foil [11], energy loss of the pro-jectiles in the gas and a typical opening angle of the sample of ±5°) and for the samedissipated power of 0.2 W in the entrance foil. Under these conditions, the yieldfrom p-T is about a factor of two higher than that of d-D. In time of flight experi-ments, the p-T reaction is even more advantageous because of the better time resolution.
2.2. Neutron background and target structure
In general, in neutron activation work, the signal to background ratio cannotbe increased by improving the energy resolution of the set-up. The backgroundcannot simply be determined by integration over its energy distribution. The neu-tron flux within each energy bin must be weighted with its effectiveness. Since theenergy dependence of the activation cross-section differs from case to case, onlythe intensity of the integrated background can be considered here and not itseffectiveness.
The intensity of the neutron background in an actual experiment depends ona mixture of physical properties and technical possibilities. The latter cannot bedealt with in much detail because they are strongly dependent on the individualset-up. Thus, only general guide-lines will be given.
The physical properties of a source relevant to the background intensity are:
(1) The intrinsic background from the source reaction (breakup neutrons orneutrons from excited target nuclei or neutrons from a second line at forwardangles when the velocity of the centre of mass is larger than that of the neutronin the cm. system).
(2) The angular dependence of the energy and intensity of the primary neutrons.
The signal to background ratio from the first property is independent of the experi-ment. In the monoenergetic range indicated by the heavy lines in Fig. 2, thereis no such background. When it shows up the intrinsic background cannot be sub-tracted experimentally by a background run. However, a correction can be calcu-lated from known differential cross-sections of the background reaction.
The room background (scattering from air and any objects in the experi-mental area and its environment) is affected by the anisotropy of the intensityand of the energy of the neutron emission. For experiments at 0°, strong anisotropiesof both properties give maximum signal to background ratios. However, for asimultaneous measurement at several angles, a small anisotropy of the differentiallaboratory cross-section will be better.
In Fig. 3, the anisotropy of the differential cross-section is expressed by theratio of the 0° value over the angle integrated value. Three main classes of cross-section anisotropies can be discerned:
(a) (Nearly) isotropic: d-T near threshold(b) Strong forward peaking: d-D for higher energies(c) Containment of neutrons in a forward cone: t-H, 7Li-H.
90 DROSG and SCHWERER
En IMeVJFIG. 3. Energy dependence of the forward peaking of the differential laboratory cross-sections.Inside the monoenergetic range of each reaction the curves are full. Isotropic neutron productiongives a value of 0.08.
En C MeV ]
FIG. 4. Energy dependence of the forward peaking of the neutron energy distribution. Theneutron energy at 90°is compared with that at 0°, except for 'contained'neutrons, where 30°iscompared with 0 . Inside the monoenergetic range the curves are full.
PART 1-3 91
The last class depends on the confinement of the neutrons into a forward conewhen the velocity of the centre of mass is larger than the cm. velocity of the neu-tron. This confinement gives minimum room background and simplifies shielding.However, at each angle inside the cone there will be two neutron groups withdifferent energies.
For negative Q-value reactions which are of interest here, the half-angle © ofthe cone for projectiles of energy Ejj, can be derived from the equation
M2M4sin2© =
M,M3
The masses M; are those of the projectile, the target, the neutron and of the residualnucleus, respectively, while E^ is the threshold energy of the reaction in question.The cone opens with increasing energy E^ and the energy of the transition fromthe double-valued to the single-valued region can be obtained by setting Eq. (1)equal to 1.
For the t-H and the 7Li-H reactions mentioned above, the mass factor inEq. (1) is close to 1 so that in both cases © is given approximately by
0 = arcsin 1 - —E
(2)
This approximation agrees, to better than 0.1°, with the relativistic results for allincoming energies that are considered here.
In Fig. 4, the decrease of the neutron energy with the laboratory angle ispresented by the ratio of the energy at 90° (or, for contained neutrons, at 30°) overthe energy at 0°. A strong decrease with angle (as in the p-T case), i.e. a strong'anisotropy' of the energy, reduces the effectiveness of room background, espe-cially in reactions (or detectors) which are insensitive to lower energy neutrons.
The structural background stems from the interaction of the incoming chargedparticle beam with matter other than the actual target isotope. Usually contribu-tions from the machine (beam line) and the target structure (including the beamstop) will be noticed. This background should be minimized by using high Z mate-rials (such as gold, tantalum and platinum) in the case of deuteron beams and(isotopically pure) materials with sufficiently high (p, n) thresholds for protonbeams. In the case of deuteron beams, carbon, stemming from hydrocarbonatesin the vacuum system and deposited on the target, is often a source of backgroundneutrons. Therefore, either cold traps must remove the hydrocarbonates from thevacuum or hydrocarbonates must be avoided, e.g. by using mercury diffusion pumps.
The structural background can be subtracted experimentally, at least to afirst order, by substituting the neutron production target with a dummy of thesame construction, but without the actual target isotope. For thick targets there
9 2 DROSG and SCHWERER
will be a noticeable over-correction due to the absence of the energy loss in thetarget isotope.
2.2.1. Gas targets [12, 13}
For gaseous targets the evacuated gas cell can serve as the dummy for the back-ground run. In favourable cases, such as the p-T reaction, a dummy gas with asufficiently high neutron production threshold (in our example, H2) can be used tomake up for the energy loss by the target isotope.
The entrance foil of a gas target which separates the gas from the vacuum of thebeam line must be of a material with the following, in some respects contradictory,properties:
(1) Good mechanical strength to withstand a pressure difference of severalatmospheres.1
(2) Good thermal conductivity to avoid an excessive local temperature at thebeam spot.
(3) Small neutron production cross-sections to minimize the intensity of back-ground neutrons.
(4) A low atomic number and/or a small areal density to minimize energy lossand straggling of the incoming beam.
Commonly used materials are Havar2, nickel, molybdenum, tantalum and tungstenin thicknesses of several pm [3].
A practical very low background cell for the p-T reaction would have a 58Nientrance foil and a 28Si beam stop [14]. However, when nickel is heated (e.g.locally by an intense beam), it becomes slightly permeable for the hydrogen isotopes,resulting in small losses of tritium into the vacuum system. No leakage is observedwhen a molybdenum foil is used as the entrance window. The high gamma fluxassociated with such a low neutron background cell should not matter in activationwork. A more detailed comparison of monoenergetic neutron sources with respectto the background can be found in Refs [14] and [15].
The advantages of gas targets are:
(a) Convenient determination of the areal density of the target isotope bypressure and temperature measurements, continuously during the experiment;
(b) Even areal thickness of the target isotope;(c) Convenient background subtraction after emptying the cell (or replacing the
target isotope with a suitable dummy gas, if available);(d) Easy adjustment of the areal thickness of the target isotope by pressure
adjustment.
1 standard atmosphere (atm)= 1.013 25 X 10s Pa (pascal).Hamilton Watch Company, Lancaster, PA, USA. Havar is a complex alloy of Co, Fe,Ci and Ni.
PART 1-3 93
The disadvantages are:
(i) The entrance foil gives an energy loss and adds to the effective neutron energyspread because of angular and energy straggling, thus causing problems withvery thin targets;
(ii) The entrance foil adds to the neutron background;(iii) A longer target because of the smaller density of the target isotope, giving a
less favourable geometry (and worse time resolutions which can be importantin time of flight experiments);
(iv) The effective target thickness depends on the beam current (beam heating).
The beam heating not only affects the actual neutron flux, but also the effectiveneutron energy. The safest way to correct for the beam heating effect is to deter-mine it experimentally by monitoring the dependence of the flux on the beamcurrent under otherwise constant experimental conditions. For a straightforwardcalculation of the beam heating effect, the mean gas temperature in the target celland in the dead volume of the filling system, as well as the ratio of cell volume todead volume, must be known.
3. PARAMETRIZATION OF THE DIFFERENTIAL CROSS-SECTIONS
As has been pointed out earlier (Ref. [4]), the uncertainties in the effectiveprojectile energy and in the actual 0° position are sometimes much more seriousthan those of the differential cross-sections themselves. Figure 5 gives the energydependence of the relative change in the 0° cross-section for a 1% change in the pro-jectile energy. This effect is very serious for the p-7Li reaction (up to 30%) andeven more so for the 7Li-H reaction (with a maximum of 50% at 16 MeV). Thelatter reaction is not shown because its structure would not be resolved in thefigure.
Figure 6 shows the maximum percentage change of the differential cross-sections for a 0.1° offset of the 0° direction. The curve fort-D coincides with thep-T curve above 7 MeV and falls rapidly below that energy. The other two inversereactions (with their contained neutron emission) are omitted for obvious reasons.
These uncertainties not only affect the reference data, but they must also beconsidered in the experiment in which these data are needed. Therefore, theeffective beam energy and/or the actual 0° position must be determined carefullyif their uncertainties contribute too much to the total error. The uncertainty in the0° position can be cancelled to a first order by performing the experiment both tothe left and to the right of the incident beam.
The data presented here are not a collection of all of the experimental results,but rather their presentation in consistent sets of Legendre coefficients. Thesecoefficients were taken from the latest available evaluations. Their accuracies are
94 DROSG and SCHWERER
0.2
3
2
.u 1
z
MIV
E C
H/
REL
-2
-
„
d - T ^ ^
' ' ' ' I
- ^ _
p-T ,
^—
!
| 1
/
p-'li
- •\jf\f\-K1 2
PROJECTILE ENERGY [MeVJ
- -20
FIG. 5. Percentage change in the 0 cross-section for a 1% change in the projectile energyfuse the right-hand scale for the p-nLi reaction).
1 2 5 10 20
PROJECTILE ENERGY [MeV]
FIG. 6. Maximum percentage change in the differential cross-sections at a given projectileenergy when the 0°position is offset by 0.1°.
PART 1-3 95
discussed later for each reaction. The presentation follows that of Liskien andPaulsen [9]. The absolute differential cm. cross-section at an angle 0 is given by
where P; are the Legendre polynomials and A; the reduced Legendre coefficients.The reaction kinematics data (thresholds and neutron energies) were calculated
relativistically using nuclear masses derived from atomic mass tables [16]. Thegraphs within each section are meant to provide a convenient overview of theenergy and angular dependences of the neutron energies and the laboratory cross-sections. Accurate calculations can be performed using the tables containing theLegendre coefficients and the short, interactive, self-explanatory computer codegiven in the appendix of this paper. A more sophisticated program, which inter-polates non-linearly and includes the Legendre coefficients, can be obtained fromthe Nuclear Data Section (Division of Research and Laboratories) of the IAEA.
3.1. Interaction of protons with tritons
Table II gives the reduced cm. Legendre coefficients for the 3H(p, n)3Hereaction. These coefficients are taken from Ref. [4] for incoming energies, E^,,of 13 MeV and higher. At lower energies a new evaluation was performed [8]which included angular distributions of the 'H(t, n)3He reaction for energies E^between 1.99 and 6.40 MeV and other new p-T data [17].
The scale error of the evaluated data increases from about ±1.5% between 10and 16 MeV to about 4% at energies of 3 MeV and lower. The shape error of theangular distributions is close to ±2% between 3 and 14 MeV; it increases to ±3%at 16 and at 2.5 MeV and becomes even higher below 1.3 MeV. The uncertaintyin the 0°position is typically ±0.1° with a maximum of ±0.6° near 3 MeV. Theenergy uncertainty is approximately ± 0.02 MeV and decreases with decreasingenergy.
Since there are not enough independent data with adequate agreement avail-able on both sides of the resonance at 3.1 MeV, the error estimate given here mightbe optimistic in this energy range. Other original papers on which this evaluationis based are listed in Refs [4, 5, 9].
3.1.1. 3H(p,n)3He
Above 0.7 MeV this reaction has the highest yield, if the ^ ( t , n)3He reactionis disregarded. Below En = 0.7 MeV, 7Li(p, n)7Be is the better choice, not onlybecause of the higher specific yield between 0.45 and 0.7 MeV, but alsobecause of the ease in producing thin targets with good energy resolution. In addi-tion, the relative kinematic energy spread at 0° (owing to the finite opening angle
TABLE II. THE 3H(p, n)3He REACTION
(Proton energy: Ejn; cm. differential cross-section at 0°: So; reduced Legendre coefficients: A(; cm. differential cross-sectionat 180°: Sn; integrated cross-section: S()
jn o
(MeV) (mb/sr)A7
(mb/sr) (mb)
1.20 14.9 1.072 -0.150 0.0781.30 17.55 1.1070 -0.2460 0.13891.40 19.55 1.1365 -0.3550 0.21851.50 21.22 1.1688 -0.4593 0.2947 -0.0042
1.60 22.56 1.1985 -0.5455 0.36.15 -0.01451.70 23.67 1.2229 -0.6252 0.4265 -0.0263 0.00221.80 24.60 1.2396 -0.6918 0.4868 -0.0376 0.0046 -0.00171.90 25.94 1.228.1 -0.7285 0.5460 -0.048.1 0.0068 -0.00432.00 28.39 1.1789 -0.7280 0.6023 -0.0556 0.0086 -0.0062
2.10 31.69 1.1149 -0.7035 0.6470 -0.0613 0.0098 -0.00692.20 35.38 1.0515 -0.6725 0.6817 -0.0650 0.0107 -0.0074 0.00082.30 39.50 0.9860 -0.6365 0.7129 -0.0680 0.0114 -0.0075 0.00172.40 43.60 0.9300 -0.6032 0.7370 -0.0704 0.0119 -0.0076 0.00222.50 47.03 0.8877 -0.58.12 0.7603 -0.0745 0.0125 -0.0076 0.0028
2.60 50.15 0.8495 -0.5597 0.7796 -0.0779 0.0131 -0.0076 0.00322.70 52.28 0.8254 -0.5469 0.7948 -0.0828 0.0137 -0.0077 0.00352.80 53.86 0.8067 -0.5348 0.8060 -0.0885 0.0.145 -0.0078 0.00382.90 54.93 0.7920 -0.5250 0.8160 -0.0949 0.0157 -0.0079 0.00423.00 55.72 0.7806 -0.5.195 0.8269 -0.10.15 0.0170 -0.0079 0.0045
.19.4 201.26.2 24 4.233.4 279.240.9 31.1.7
47.8 339.754.5 363.760.6 383.266.5 400.473.2 420.6
BO.6 444.088. .1 467 .695.7 489.3
103.0 509.5109.4 524.6
1:14.9 535.31.18.9 542.3121.9 546.0123.9 546.7125.8 546.5
OOwaav><->
m
3.20 56.23 0.7624 -0.5.138 0.8515 -0.1168 0.0198 -0.0084 0.0053 128.1 b38.73.40 55.55 0.755.1 -0.5.175 0.8767 -0.1355" 0.0240 -0.0090 0.0062 129 1 527 I3.60 53.84 0.7556 -0.528.1 0.9042 -0.1584 0.0295 -0.0098 0.0070 I28.'o 511.23.80 51.48 0.7618 -0.5418 0.9336 -0.1868 0.0359 -0.0.108 0.0080 127.6 492.84.00 48.96 0.7709 -0.557.1 0.9633 -0.2178 0.0435 -0.0119 0.0090 126.0 474.4
4.50 42.37 0.8123 -0.5998 1.0241 -0.3024 0.0691 -0.0.153 0.0.120 120.1 432.65.00 36.36 0.8616 -0.6520 1.0866 -0.3958 0.1047 -0.0.197 0.0155 -0.0009 114.1 393.75.50 30.88 0.9170 -0.7163 1.1700 -0.5122 0.1^99 -0.0256 0.0.196 -0.0024 1083 ,15b. fl6.00 26.27 0.9750 -0.776.1 1.25.13 -0.6454 0.2070 -0.0329 0.0246 -0.0043 102.9 321.86.50 22.20 1.0404 -0.8454 1.3330 -0.7903 0.2809 -0.0423 0.0305 -0.0066 97.3 291.3
7.00 19.06 1.1117 -0.906B 1.3914 -0.9372 0.3673 -0.0550 0.0373 -0.0089 91.8 266.3 >7.50 16.77 1.1745 -0.9374 .1.4040 -.1.0607 0.45B0 -0.0706 0.0440 -0.0.117 86.6 247. S H8.00 15.30 1.2045 -0.9294 1.3542 -.1.1202 0.5423 -0.0871 0.0500 -0.0144 81.1 231.68.50 14.54 1.1931 -0.8758 .1.2566 -.1.1144 0.6035 -0.10.17 0.0547 -0.0:160 75.8 2:10.0 w9.00 14.29 1.1555 -0.7892 .1.122.1 -.1.063:1 0.6473 -0.1135 0.057.1 -0.0162 70.9 207.5
9.50 14.53 U0955 -0.6851 0.9790 -0.97?.? 0.6587 -0.1200 0.058.1 -0.0141 66.6 200.110.00 14.9.1 .1.0338 -0.5834 0.8480 -0.8807 0.6559 -0.12.13 0.0584 -0.0108 62.5 193.711.00 .16.35 0.8780 -0.4057 0.6399 -0.6787 0.6245 -0.1090 0.0557 -0.0046 54.8 178.212.00 17.85 0.7328 -0.2624 0.4940 -0.4948 0.5708 -0.0956 0.0548 0.0005 48.3 .164.413.00 19.73 0.6131 -0.1527 0.4052 -0.3520 0.5084 -0.0809 0.0526 0.0049 0.00:14 42.6 .152.0
14.00 2.1.50 0.5219 -0.0684 0.3437 -0.2478 0.4571 -0.0677 O.OblO 0.008.1 0.0039 -0.0018 37.7 14 1.015.00 23.02 0.4530 -0.0036 0.3023 -0.1725 0.4:117 -0.0543 0.0504 0.0108 0.0069 -0.00V/ .13.3 131.0.16.00 24.38 0.3983 0.0445 0.276.1 -0.1:151 0.3710 -0.0423 0.0505 0.0133 0.0095 -0.00!i8 29.5 122.0
98 DROSG and SCHWERER
TABLE III. Q-VALUES, THRESHOLDS AND NEUTRON ENERGIES ATFOR p-T(AH energies in MeV)
Exit channel
Ein
1.019
1.147
8.354
11.328
Q
En(0°c.m.)
0.064
0.288
7.585
10.560
n + 3He
En(180°c.m.)
0.064
0.000
•0.764
n + p + d
Enmaxl
0.525
4.561
-6.257
2n + 2p
Enmax2
0.712
-8.482
of the sample) is about twice that of p-7Li, namely, 0.3% for a half-angle of 5°(see Fig. 1). For a 1% change in the proton energy the 0° cross-section changesby more than 1% between 1.9 and 2.6 MeV, between 3.8 and 8.1 MeV and near12.5 MeV (see Fig. 5 ).
Table III summarizes the relevant reaction data, Figs 7-13 illustrate theangular dependence of the neutron energies and differential cross-sections. Above aproton energy of 8.354 MeV (En(0°) = 7.585 MeV), a continuum of breakup neutronswill be present with a maximum energy (En m a x) which is typically 6 MeV less than thatof the primary neutrons. Above 11.328 MeV, another source of breakup neutrons willcontribute to the continuum. However, the intensity of the continuum is muchless severe than in the d-D case, so that experiments even at 14.4 MeV neutronenergy [18] are feasible (with an intensity 25 times higher than that of the d-Tresonance neutrons). As was discussed earlier the structural neutron backgroundcan be reduced by using materials with high (p, n) thresholds. Measurements ofthe breakup cross-section are collected in Ref. [5], while a recent measurement [19]also includes breakup spectra.
3.1.2. lH(t,n)*He
This reaction has the highest yield (for En > 1.7 MeV) among all known mono-energetic reactions. Between 5.6 and 11.4 MeV, the yield is at least ten times largerthan for the competing p-T reaction. Up to 17.64 MeV, the reaction is intrinsicallymonoenergetic.
In addition, the background situation is very good, because neutrons are onlyemitted into a forward cone with a half-angle © according to Eq. (2).
Text cont. on p. 111.
PART 1-3 99
THE 3H(p,n)3He REACTION
60n
0.0100
OO
oJOoV)OCD
3D.V>
na
ino
FIG. 7. (a) Neutron energy values and (b) differential cross-sections for the 3H(p, nj^He reaction: 1.3-1.7 MeV.
1.6 -r
1.4
1B0
90
8 0 -
20-|
10
' ZMMeV
30 60 90 120 150 1B0
>
FIG. 8. (a) Neutron energy values and (b) differential cross-sections for the 3H(p, n)3He reaction: 1.8-2.3 MeV.
120
0.4-
0.2-30 1B0
O
20
oOVI
a
SOw73
100
FIG. 9. (a) Neutron energy values and (b) differential cross-sections for the 3H(p, n)3He reaction: 2.4-3.0 MeV.
120
100
•0
160
FIG. 1 0. (a) Neutron energy values and (b) differential cross-sections for the 3H(p, nfhle reaction: 3.1-4.0 MeV.
5 . 5 -
5 -
4 . 5 -
0 . 5 -30 CO 90
1 I 'lfiO 180
: 5.0 MeV
i 5.5 MeV
' 6 . 0 MeV; .6.5 MeV
10
voVIOw
g.
awSBW7
ISO 1B0
FIG. 11. (a) Neutron energy values and (b) differential cross-sections for the 3H(p, n)3He reaction: 4.5-6.5 MeV.
2 -
! 7.0 MeV
30 60 901 I '120 150 1130
s
ino
FIG. 12. (a) Neutron energy values and (b) differential cross-sections for the 3H(p, n)3He reaction: 7.0-9.0 MeV.
16-r
14-
12-
10-
50
X)
a" 10
3-
(b)
rpff
r ; • • \ • • : /
: • • -A" 1 /
O
OonOu
aaV)
nwtn
160 30 60 90 120 lfiO 1110
FIG. 13. (a) Neutron energy values and (bj differential cross-sections for the 3H(p, n)3He reaction: 10-16 Me V.
PART 1-3 107
THE ^ ( t ^ H e REACTION
2.5-
1.5-
5.5 MeV
5.0 MeV
4.5 MeV
4.0 MeV
1000
0.5-
5 MeV
5.0 MeV
4.f> MeV
1.0 MeV
OOO
OOO
(/IO
M
/ 4. Neutron energy values and (b) differential cross-sections for the lH(t, n)3He reaction: 3.5-5.5 MeV.
1000
100
2-
9.0 MeV
6.0 MeV
7.5 MeV
7.0 MeV
6.5 Mey
6.0 MeV
( b )i ' ' • ' i i
20 30 40 50 80 70ylab
3
FIG. 15. (a) Neutron energy values and (b) differential cross-sections for the 'H(t, n)3He reaction: 6.0-9.0 MeV. oo
1000
100
T 3od>-<u
a%T3
18 MeV i
20 MeV :
FIG.
60 70'l«b "lab
16. (a) Neutron energy values and (b) differential cross-sections for the lHft, nfhte reaction: 10-20 MeV.
ICA
n
m
PART 1-3 111
TABLE IV. Q-VALUES, THRESHOLDS AND NEUTRON ENERGIES AT 0\h
FOR t-H(All energies in MeV)
Exit channel n + 3He n + p + d 2n + 2p
E *
3.051
25.011
33.913
Q
En(0°c.m.)
0.573
17.640
24.347
-0.764
End 80°
0.573
0.019
0.014
.m.) E n m a x l
4.694
14.569
-6.257
E n m a x 2
6.362
-8.482
As shown in Figs 14-16, the second neutron group at 0° (correspond-ing to emission at 180° in the cm. system) becomes very low both in energyand intensity with increasing triton energy so that it may be neglected in manycases (see also Table IV). The main disadvantage is the radioactivity of the tritonbeam, and the need for a rather high beam energy. The latter has limited up tonow the routine use of this source to neutron energies below 13 MeV. In addition,the high triton energy gives a rather high structural background.
The kinematic energy spread is approximately three times as large as in the p-Tcase, e.g. at a half-angle of 5° for the aperture of the sample, the relative energyresolution for neutrons between 2 and 20 MeV is close to 1% (see Fig. 1).Table IV gives the relevant kinematic data and Table II the relevant reducedcm. Legendre coefficients for the differential cross-sections. However, the EJJJvalues in the latter table must be multiplied by 2.9937 and 0 must be changedto 180°— © in order for those data to be valid for the t-H case.
3.2. Interaction of deuterons with deuterons
3.2.1. 2H(d,nPHe
The data in Table V are from Liskien and Paulsen [9] for incoming energies< 3 MeV and from Ref. [4]. The anisotropy at low energies, as given by Liskienand Paulsen [9], agrees with recent accurate measurements [20], resolving thediscrepancy suspected near 0.2 MeV [5]. By including these new data the scale ofthe cross-sections below 0.4 MeV can be improved as compared with the originalevaluation [9]. These new data have shape errors of 1% and scale errors of 1.5%.
TABLE V. THE 2H(d, n)3He REACTION(Deuteron energy: £,„; cm. differential cross-section at 0°: So; reduced Legendre coefficients: ~A,; integrated cross-section: St)
E in So Ao A s A,, A6 Ao A1 0 AJS AJ I , A 1 6 S t
(MeV) Imb/sr l (mb)
0. 28I . 17<1.694 . 636. B5
9. 19I 1. 651 4 . 1 O1 6 . b *>.37.0 g
35.6 g'13. 3 O.SO. 3 £So. 7 BB63. 0 *
m67 .7 m7rl'.Li »77.0a 1.3Hh.?
BB.?PO.b9P. 79'i. 996.9
9B. 399. B
.10.1. B103.7
0.020.030.040.050.06
0.07O.Ofl0.090.100.15
0.200.250.300.350.40
0.450.500.550.600.65
0.700.75O.BO0.850.90
0.95.1.001.101.201.30
0.0270.1190.2820.500.76
1.041 * +
:K651.953.39
4.685! 917. 108.259.4
10.411.412.413.414.3
15.115.016.517.217. 8
IB. 419.020.02.1.02.1.9
0.8190.7850.7580.7370.719
0.7050.6920.6810.67:10.633
0.6050.5830.5640.5470.532
0.51B0.5060.4940.4B30.474
0.4650.4560.4470.4390.432
0.4250.4180.4050.3930.381
0.18.10.2150.2410.26:10.279
0.2920.3040.3140.3230.356
0.3790.3950.4080.4 IB0.426
0.4330.4370.4400.4430.444
0.4450.4460.4450.4440.443
0.4410.4390.4340.4280.422
0.00.10.0020.002
0.0030.0040.0050.0060.011
0.0:160.0220. 0280.0350.042
0.0490.0570.0660.0740.082
0.0900.0980.1 OB0.1170.125
0. 1340. 1420. 1580.1740.189
0.00 10.0030.0050.0 OB
1.401.501.601.70.1.80
1.902.002.102.202.30
2.402.502.602.702.80
2.903.003.504.004.50
5.005.505.806.006.20
7.008.009.00
10.001.1.00
12.00.12.3!13.0014.0015.00
22.723.4
24! 625.2
25.826.426.927.528.0
28.428.929.329.830.3
30.73.1.233.435.537.1
38.640.040.84 1.34.1.0
43.545.045.946.146.0
45.745.645.344.744. 1
0.3700.3600.35:10.3420.334
0.3260.3180.3110.3040.298
0.2930.2870.2820.2770.272
0.4160.4100.4040.398
0.2030.2160.2280.24 0
0.3P2 0.251
0.3870.3820.3770.3720.367
0.3620.3570.3!S30.3490.345
0.268 0.3410.262 0.3370.241 0.32.1
0.2600.2700.2790.2870.294
0.3010.3080.3140.3200.326
0.3310.3370.358
0.0.1.10.0.140.0 170.0200.023
0.0270.0300.0330.0370.04 1
0.0440.0480.0510.0540.057
0.0600.0640.080
0.2233 0.3060 0.3697 0.0950 0.00600.2103 0.2930 0.3763 0.1090 0.01.14
0.1990 0.28.19 0.3792 0.1224 0.01750.1892 0.2721 0.3796 0.1347 0.0232 0.00120.1837 0.2656 0.3783 0.14.17 0.0266 0.0038 0.00030.1804 0.2615 0.3775 0.1460 0.0287 0.0051 0.00080.1769 0.2584 0.3757 0.1505 0.0311 0.0062 0.0011 0.0001
1659 0.2465 0.3690 0.16(54 0.0400 0.0093 0.0020 0.0009.1552 0.2364 0.3589 0.1836 0.0496 0.01.18 0.0027 0.0018
10b. 5105. 910b. 9I Oh. 8105. 7
105.5105.3105.2105.0.104.8
104.5104.3104.0103.8103.5
103.2102.8101.299.698. 0
96.595. 094. 193.59?. 9
90.687 .885. 082.479.0
0.1477 0.2284 0.3489 0.1977 0.0568 0.0.142 0.0036 0.00270.1425 0.222(5 0.3382 0.2093 0.0629 0.0I6b 0.0040 0.00360.1383 0.2.177 0.3275 0.2196 0.0684 0.0.189 0.0052 0.0044
0.J348 0.2.136 0.3167 0.2287 0.0738 0.02.13 0.0060 0.005.1 77.40.1340 0.2122 0.3133 0.2312 0.0753 0.0220 0.0063 0.0053 0.0004 76.60.13.16 0.2098 0.3057 0.2362 0.0792 0.0236 0.0068 0.0058 0.00 13 75.00.1290 0.2070 0.2948 0.2423 0.0843 0.026.1 0.0077 0.0064 0.0024 72.60.1266 0.2045 0.284? 0.2481 0.0893 0.0285 0.008b 0.0068 0.003!. 70.3
7*H
U>
114 DROSG and SCHWERER
TABLE VI. Q-VALUES, THRESHOLDS ANDNEUTRON ENERGIES AT 0 ° ^ FOR d-D(All energies in MeV)
Exitchannel
Ein
0.000
4.451
8.904
Q
n + 3He
En(0°c.m.)
2.449
7.706
11.986
+ 3.269
n + p + d
Enmaxl
0.557
5.512
-2.225
2n + 2p
^nmax2
1.114
-4.449
Liskien and Paulsen give an absolute deviation of the reduced Legendre coefficientsof 0.01 (resulting in worst-case shape uncertainties between ±2.8% at 0.4 MeV and±7.1% at 3 MeV), a 4% relative deviation of the 0° cross-section and a 5% relativedeviation of the integrated cross-section.
The scale uncertainty between 5 and 12 MeV is approximately ±1%, while theshape uncertainty between 5 and 10 MeV is close to ±1%, increasing to about ±4%at 17 MeV. The 0° position has an error of ±0.1° and the incoming energy has atypical uncertainty of ±0.02 MeV which decreases with decreasing energy. Relevantpapers are listed in Refs [4, 5 and 9].
The monoenergetic range extends from 2.45 to 7.71 MeV neutron energy at0°. At energies that are not too low, the yield is strongly forward peaked (seeFig. 3), which gives a reduced in-scattered background. On the other hand, thisstrong angle dependence even in the neighbourhood of 0° makes it necessary tointegrate the differential cross-sections over the opening angle whenever this angleis larger than l°-2° Not to do so may result in systematic errors of a few per cent.
Above 4.45 MeV deuteron energy, the deuteron breakup gives a neutroncontinuum with an energy gap at 0° between its maximum and the primary neu-trons of, typically, 7 MeV. The intensity of this intrinsic background increasesrapidly with energy, severely limiting the usefulness of the d-D source outside of itsmonoenergetic range.
Often there is no choice other than to use the d-D reaction for monoenergeticneutron production, despite its lower yield in primary neutrons (see Fig. 2 andTable I ) and higher yield in background neutrons [14] when compared with thep-T reaction.
Text com. on p. 121.
PART 1-3 115
THE 2H(d,n)3He REACTION
3.4 -, T :
3.2-
1.8
oOVIOSaoSm
l f)0
FIG. 1 7. la) Neutron energy values and (b) differential cross-sections for the 2H(d, n)3He reaction: 0.02-0.3 MeV.
4.5
1.5-l f iO 100
o.n Mcv
_i L0.7 McV
0.6 McV
5
i no 1(10
FIG. 18. (a) Neutron energy values and (bj differential cross-sections for the 2H(d, nJ3He reaction: 0.4-0.9 MeV.
1.5
50 T.
3o :io no 90 mo mo ino 0
°lab "lab
FIG. 1 9. (a) Neutron energy values and (b) differential cross-sections for the 2H(d, n)3He reaction: 1.0-2.5 MeV.
00
oO
v>OEC
7iW73
11)0
A 6
pa
FIG. 20. (a) Neutron energy values and (b) differential cross-sections for the 2II(d, n)3He reaction: 3-7 MeV.
JOVIOta9a.VIoSBWJOM
o - - .100
F/G. 21. (a) Neutron energy values and (bj differential cross-sections for the 2H(d, n)3He reaction: 8-18 MeV.
PART 1-3 121
Data contaminated by d-D breakup neutrons have been corrected by one ofthese two procedures:
(1) An experimental subtraction of the background contribution is done by using3He as a dummy gas, which is reported to give a similar breakup spectrum [21 ].
(2) The effect of the background neutrons is subtracted by a calculation [22]using measured double-differential breakup cross-sections (d2a/dEd£2).Breakup cross-sections and sources of the original data are listed in Refs [4, 5,14, 22, 23].
Other disadvantages of the d-D reaction (as compared with the p-T reaction)are a lower projectile energy, which gives a bigger energy loss (and therefore strongerheating) in the entrance foil; larger straggling and a worse time resolution (onlyimportant in time of flight applications); and the self-target buildup in the beamstop which gives additional low energy background neutrons (noticeable after longuse of the same target) when the deuteron energy is increased. Owing to the ratherhigh yield of the d-D reaction, this latter effect is not so pronounced as in the d-Tcase. In addition, the differential cross-sections of the d-D reaction have a muchstronger angle dependence (see Fig. 6 ). Above 4 MeV deuteron energy, a changein the 0° direction by 0.1° results in a maximum cross-section change of more than1%. Table VI summarizes the relevant reaction data and Figs 17-21 illustratethe angular dependence of the neutron energies and of the differential cross-sections.
3.3. Interaction of deuterons with tritons
The data in Table VII were derived from Ref. [24] (<0.4 MeV), from Ref. [9]« 2 . 9 MeV), from Ref. [6] (<9.5 MeV) and from Ref. [4]. Below 0.4 MeV thetypical total error is less than 1.5%. For the 0.4 to 2.9 MeV range, Ref. [9] gives anabsolute deviation of 0.01 for the reduced Legendre coefficients (resulting in worstcase shape uncertainties between ±1.4% at 0.4 MeV and ±6.5% at 2.9 MeV), 3-4%relative deviation of the 0° cross-section and a 7% relative deviation of the integratedcross-section. The scale error of the two evaluations in the higher energy range isgenerally 1.5%, except near 4 MeV, where it increases to 2%. The shape error isestimated to be ±3% at 3 MeV, decreasing to ±2% between 5 and 10 MeV and thenincreasing again (+2.5% at 13 MeV, ±5% at 16.5 MeV).
The 0° position has an error of ±0.1° and the incoming energy a typical uncer-tainty of ±0.02 Me V, decreasing with decreasing energy. Sources for the relevantdata are listed in Refs [4, 5 and 9]. As pointed out [6], there is an indication thatthe scale at higher energies is too high by (1.5 ± 0.8)%.
3.3.1. 3H(d, n)4He
This reaction is best known for its resonance at 107 keV [3], culminating in apeak cross-section of about 5 b. Owing to the high Q-value (4-17.59 MeV), low
TABLE VII. THE 3H(d, n)4He REACTION(Deuteron energy: Ein; cm. differential cross-section at 0°: So; reduced Legendre coefficients: A(; cm.differential cross-section at 180°: Sn; integrated cross-section: St; the coefficients are multiplied by 1000 tosave space)
(MeV) (mb/sc)A 7 A 1 0 1 2 A1 3
0.020.030.040.050.06
0.070.080.090. 100.12
0.150. 170.200.250.30
0.350.i»00.450.500.55
0.600.650.700.75O.BO
0.901.001.101.201.30
4 . 621.755.5
106.6172.4
245.8313.9366. S393.638't. 1
306.6254.6196.6132.197.5
77.163.553.045.539.4
35.531.929.427.025.0
22.019.817.916.715.8
1000.1000.1000.1000.1000.
1000.1000.1000.1000.1000.
1000.1000.1000.1000.1000.
1000.999.998.997.995.
993.989.986.983.978.
968.957.946.931.915.
4 .1 3 .2 1 .3 0 .
3 8 .4 6 .5 3 .6 0 .(57.
7 7 .8 7 .9 4 .
100.105.
- 3 .-11.-18.-25 .
-3.1.-35 .-39.-43 .-45 .
-45 .-44.-40.-32.-23 .
1.3 .
Sn S t(mb/sc) (mb)
4 . 62.1.755.5
106.6172.4
245.8313.9366.5393.6384.1
306.62S4.6196.6132.197.5
77.163.051.643.637.0
32.829.026.323.82.1.7
18.616.414.5.13.412.5
b8.2273.697.
1339.2166.
3089.3945.4608.4947.4827.
38!i3.3200.2470.1660..1225.
969.797.66H.570.493.
443.396.364.334.307.
268.239.213..195..182.
O50OO»a.V)
oHHNM
j !mmJO
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ru XJ -o en •*•
Ok -teo ru u
ru x)Ok eo o
-j^jOk cn-e-
ru ru « i-> i-*ruook eo o
t^- ru J-* »-ruxjOkruea
ru *-k
V3 CD -0 kT. *
-J J- i—
•*• w ru ru I-*
PJ x) inO. PJ ~J
tn en *-JOUlo as ru
en eo ru
to ru XJ Ok to
-t- -f eo to ru
O -f w. CD tO
" S v O O S ^
l-i Otji o
IUIU
t— o
-JO.
Ok to x)asru tn
Ok * ru
-ooro
o. en tn
-ft- O -t- 03 *•*0. o Jr- to 33
o as — tn *
PJ tn o CD *•
•e- to co ru ru
r u o
as as
w o
toxi^OkO, w^j^cnpj
tx
to
Jr ruto o.
to eo
tUPJ
33 OS
b^ i-k x j -^ tn
-c pj tn cr. w
to to ru ru ru
o o-^ J- o05 as - j tn *
-*- to nw-e-t
< tn u
toru t
^ o o
J-05 0.
* o o
O 1t>k(
oto
ru o i - os ru co - j o, as ru
to *JJ rv - o
eo
O
i~> tn as-0 X)
to 'a) •*•Os 05 O
o ;-»to co co PJ ru >-sj tr. w co PJ x> *JJ
- ^- -e- - enpj T. to i->
cr tn en 0keo en xs r»j -
0k t i enru o as
o, -j -j -g osenruo- X) —
-»a ~i en to PJ->;ru w -ft- ru
OS OS 3D X> -CP_' tO 0k O O
ru to-*- er ~;CD -oen en *•
X>X)X) X) OPJ -t- 0k ts ru
J u ITtOO.
O O M Mtr: x) •«• x) o.
eo -f -f cr. o.pj o x> co X)
oa o. o". -«• x> to -t tn * ru
ezi e-i
124 DROSG and SCHWERER
energy accelerators can be used to produce '14 MeV neutrons (which is what isdone in many installations). Comprehensive overviews of such 14 MeV neutrongenerators are available (e.g. Refs [25, 26]).
Although there are no secondary neutrons up to 20.46 MeV, the room back-ground even at lower energies is comparatively high because of the rather smallanisotropies of the cross-sections and neutron energies. In addition, the specificyield, even at the resonance, is very low (see Fig. 2). Thus there are cases wherep-T is a better choice than d-T for experiments with 14 MeV neutrons (e.g. Ref. [18]).
After prolonged use of a target, the deuterium self-buildup in the beam stopcan become an undesired source of low energy background neutrons, especiallyafter an increase in the deuteron energy. Since secondary neutrons (with a maxi-mum energy that is about 20 MeV less than the primary neutron energy) affectmeasurements above 20.5 MeV only, there was up to now little need for breakupdata. The few measurements available are listed in Ref. [5].
Figure 22 compares the specific yields of various sources using gas targets forneutron production near 14 MeV. The advantage of using 90° rather than 0° for thed-T (and the t-D) source is obvious. At this angle the energies of the emittedneutrons are quite independent of the beam energy. However, in an actual experi-ment the neutrons intercepted by the sample will be from a finite angular rangearound 90° (depending on the opening angle of the sample and the angular stragglingof the beam). Thus the actual specific yield will be lower (even more so with solidtritium targets owing to much increased angular straggling). The reaction data arecollected in Table VIII,the angular dependence of the neutron energies and of thedifferential cross-sections are illustrated in Figs 23-30-
3.3.2. 2H(t,n)*He
Exchanging the projectile with the target nuclei of the d-T reaction increasesthe upper limit for monoenergetic neutron production from 20.5 to 23.0 MeV. Themaximum neutron yield at 0° then occurs for 15.2 instead of 14.8 MeV neutrons,so that the specific yield is higher (up to 80%) between 15.07 and 17.02 MeV.Owing to the smaller relative energy loss of the projectile, the total neutron yieldis 1.5 times higher for the same cm. conditions, which results in the higher 90°yield curve in Fig. 22.
No data on the breakup cross-sections have been published. Table IX sum-marizes the reaction data. The maximum energy of the breakup continuum isabout 22 MeV less than the primary neutron energy. The primary cm. cross-sections can be calculated by using the Legendre coefficients from Table VII,multiplying E^ by 1.4976 and changing 0 to 180°- 0 . Figures 31-34 illustratethe angular dependence of the neutron energies and of the differential cross-sections.
PART 1-3 125
10 -
2. 10 -Q
UJ
O
3 io2
10
i
-
. \ \ t -D (90°)
\d-T (90°)
/ /
/ /
1
t-H (0°)
p-t (0°)
t-D
"X—/ d-T
1
1
-
(0°)
_ _ _
Kf) '
I
I
-
-
-
-
1
14.0 14.5 15.0 15.5
NEUTRON ENERGY (MeV)
16.0
FIG. 22. Specific neutron yields from monoenergetic neutron sources near 14 MeVemploying gas targets.
TABLE VIII. Q-VALUES, THRESHOLDS AND NEUTRON ENERGIES ATFOR d-T(All energies in MeV)
Exitchannel
0.000
3.711
4.985
10.443
14.159
17.876
Q
n + 4He
En(0°c.m.)
14.028
20.461
21.964
27.891
31.717
35.465
17.589
n + p + t
Enmaxl
0.298
2.000
7.356
10.918
14.472
-2.225
2n + ^ e
Enraax2
0.400
6.416
10.006
13.573
-2.988
n + d + d
Enmax3
0.838
5.763
9.521
-6.257
2n + p + d
Enmax*
1.136
6.414
-8.482
3n + 2p
Enmax5
1.435
-10.707
1 26 DROSG and SCHWERER
TABLE IX. Q-VALUES, THRESHOLDS AND NEUTRON ENERGIES ATFOR t-D(All energies in MeV)
Exitchannel
Bin
0.000
5.558
7.466
15.639
21.204
26.771
Q
n + *He
En(0°c.m.)
14.028
23.006
25.032
32.946
38.023
42.985
17.589
n + p + t
Enmaxl
0.668
2.990
10.038
14.713
19.375
-2.225
2n + 3He
*-"nmax2
0.897
8.934
13.650
18.331
-2.988
n + d +. d
Enmax3
1.879
8.592
13.559
-6.257
2n + p + d
Enmax4
2.547
9.789
-8.482
3n + 2p
EnmaxS
3.214
-10.707
3.4. Interaction of protons with 7Li
Reduced cm. Legendre coefficients are given in Tables X and XI for the7Li(p, no)7Be and the 7Li(p, n^ 'Be* reactions, respectively (7Be* is in the0.43 MeV excited state). The coefficients used in these tables are taken fromLiskien and Paulsen [10]. For the ground state reaction they give an absolutedeviation of the reduced Legendre coefficients of 0.03 at proton energies above2.2 MeV (resulting in minimum worst case shape uncertainties of ±5.9%) and 5%for the relative deviation of the 0° cross-sections. For the reaction leading to the0.43 MeV excited state, the absolute deviation of the Legendre coefficients forproton energies above 3.2 MeV is 0.1 (resulting in minimum worst case shape uncer-tainties of ±33%), while the uncertainty in the cross-section ratio at 0° is 9%.
The quality of the evaluated coefficients in the light of more recent data hasbeen discussed [2, 3]. Recent data for the 'HC'Li, n)7Be reaction [27] show sur-prisingly large deviations of the 180° excitation function from the evaluated datanear 2.0 and 2.5 MeV proton energy which could be caused by discrepant projectileenergies [7]. From this and other evidence, it can be estimated that the accuracyof the cross-sections calculated from the coefficients will be of the order of 10%over most of the energy range. Experimental papers on the p-7Li interaction arelisted in Refs [2] and [10].
Text cont. on p. 138.
PART 1-3 127
TABLE X. THE 7Li(p, n)7Be REACTION(Proton energy: E^; cm. differential cross-section at 0°: So; reduced Legendrecoefficients: At; cm. differential cross-section at 180°: Sn; integrated cross-section: St)
EIn(MeV)
12222
22222
.95
.00
. 05
. 10
.15
.20
.25
.30
.3b
.40
2.452222
23
.50
.60
.70
.00
.90
.003.1033
33333.
3.4.4.4.4.
4.4.4.4.4.
4.S.S.5.5.
5.5.S.S.5.
5.6.6.6.6.
6.6.6.6.6.
6.7.
.20
.30
.40
.50
.60
.70
.80
.90
.00
.10
.20
.30
4050607080
9000102030
40bO607080
9000102030
40SO607080
9000
So(mb/srl
19.015121322
4679837161
b347403634
3332313029
2920282727
27.26,27.28.30.
32.34.37.41.44.
48.SO.48.45.42.
39.36.33.31.29.
26.24.22.21.19.
18.16.15.14.13.
12.12.
.0
.1
.1
.6
.7
.2
.4
.4
.2
.0
.4
.5
.0
.2
.0
.0
.2
. 5
.9
.3
.7
.2
.8
.4
.0
.7
. 1
.2
.0
.26b18
10664
66960
74605
29667
92
11111
00000
00000
00000
00000
0.0.0.0.0.
0.0.0.0.0.
0.0.0.0.0.
0.0.0.0.0.
0.0.0.0.0.
0.0.0.0.0.
0.0.
Ao
.125
.425
.805
.810
.300
.815
.bUb
. 475
.460
.44b
.465
.490
.545
. S8b
.590
.580
.575
. sao
. bOb
. b90
.600
.620
.640
.660
.68b
.710
.730
.740
.740
.720
.70S,<S6S.660.63060S
,590590600615635
655675695710725
745760775785800
810820830840850
8S0855
-0-0-0-0-0
00000
00000
0000.0.
0.0,0.0.0.
0.0.0.0.0.
0.0.0.0.0.
0.0.0.0.0.
-0.-0.• 0 .
-0.-0.
-0.-0.-0.-0.-0.
-0.-0.-0.-0.-0.
-0.-0.
A.I
. 125
.430
. 825
.845
.435
.110
.330
.430
.440
.445
.420
.400
.3bO
.320
.330
.3bO
.36b
.360
.355
.345
.330
.305
.295
.285
.275
,250,225210.200190
18016bJbS140130
11509006503S005
02S050085110135
160180205220240
255265275285295
300305
0000
00000
00000
00000
00000
00000
0.0.00.0.
0.0.0.0.0.
0.0.0.0.0.
0.0.0.0.0.
0.0.0.0.0.
0.0.
.005
.020
.03b
.055
. 075
.005
.095
.100
.110
.115
.110
.105
.095
.080
.070
.060
.060
.060
.065
.070
.075
.080
.095
.105
.125
.145
.175
.210
.260
.295
.320
.340
.355
.360
.365
.365
.365
.365
.360
.35534S.34033S330
325320316310305
305300295290285
285280
-0.-0.-0.
-0.-0.-0.-0.-0.
-0.-0.-0.-0.-0.
• 0 .
-0.-0.-0.
0.0.0.0.0.
0.0.0.0.0.
0.0.0.0.0.
A3
015040065
08510012bISO170
180170Ibb125095
07004&030015
015030050065080
090100115125135
140145150155160
0.16S0. 170
s,r<mb/tc>
2327323b42
36261186
89,12,12,11
9,0,8.B.
.75
.90
.06
.24
.26
.43
.93
.68
.57
.73
.48
.48
.15
.96
.63
.90
.64
.74
.849.27
9.11.12.14.15.
18.20.22.25.28.
32.34.37.39.41.
43.4b.45.43.41.
40.38.36.34.32.
30.28.
.96
.19
.41
.1889
0903493880
20
508766
IISO207898
3906274419
4430
26.6724.23.
22.20.19.18.17.
16.15.
9960
3996SO4040
3049
st(tub!
269.269.275.298.392.
478.502.498.413.342.
310.292.277.265.253.
241.232.227.223.222.
221.224.227.231.236.
241.245.252.262.271.
28b.£J9B.
311.325.341.
Jb7.371.366.352.338.
326.310.296.,282.264.
250.233.220.207.196.
185.174.163.154.146.
138.131.
128 DROSG and SCHWERER
TABLE XI. THE 7Li(p, n)7Be* REACTION(Proton energy: Ein; cm. differential cross-section at 0°: So; reduced Legendrecoefficients: At; cm. differential cross-section at 180°: Sn; integrated cross-section: St)
E i n(MeV)
2 . 52 . 62 . 72 . 8
2 . 93 . 03 . 33 . 23 . 3
3 . 43 . 53 . 63 . 73 . 8
3 . 94 . 04 . 14 . 24 . 3
4 . 44 .B4 . 64 . 74 . 8
4 . 95 . 0S . I5 . 25.3
5 . 45 . 5b . 65 . 75 . 8
5 . 96 . 06 . 16 . 26 . 3
6 . 46 . 56.66 . 76 . 8
6.97 . 0
So Ao(rnb/sr)
0.651.101.451.75
2.052.2b2.402.602.7b
2.8b2.953.003.053.05
3.0b3.053.002.902.85
2.802.752.702.652.60
2.602.652.702.803.10
3.554.004.555.105.60
6.156.506.957.2b7.40
7.206.756.2b5.805.30
4.7b4.25
1.010.1. 0951.2751.540
1. 7551.88b1.9051.8651.780
1.7001.58b1.48b1.3901.335
1.3001.2801.2801.28b1.290
1.2901.2901.2901.2851.275
1.26b1.2301.1801.1100.970
0.8400.7450.6650.6000.560
0.525O . b l b0.5200.5250.53b
0.5450.5600.5800.6000.630
0.6550.675
A I
0 . 0 0 0-0.025-0.080-0.220
-0.310-0.355-0.400-0.415- 0 . 4 4 0
-0.470-0.490-0.515- 0.535- 0.550
-0.570- 0.58b-0.600-0.610-0.615
- 0.620- 0.620-0.615-0.610-0.600
-0.585-0.550-0.500-0.420-0.280
-0.140-0.0450.0100.0500.080
0.10b0.1300.14b0.1550.165
0.1700.1750.1800.1850.190
0.1950.200
•0.005-0.020-0.050-0.115
-0.220-0.315-0.3bb- 0.34 5-0.27b
-0.210-0.115•0.0200. 1250.240
0.3400.4200.4750.5200. 555
0.5900.6150.6300.6450.655
0.6600.6600.6550.6400.620
0.580O.bbO0.5250.5000.470
0.44b0.4000.3600.3250.290
0.2600.2300.2000.1700.135
0.1050.080
A 3
-0.005-O.ObO-0.145-0.205
- 0.225-0.215-0.150-0.105- 0 . 0 6 b
-0.0200.0200.0500.020
-0.025
-0.070-0.115-0.155-0.195-0.230
-0.260-0.285-0.305-0.320-0.330
-0.340-0.340-0.335-0.330-0.310
-0.280-0.250-0.200-0.150-0.110
-0.075-0.045-0.025-0.005
0.0.10
0.02b0.0350.0400.0450.04b
0.04b0.045
(mb/ sc)
0.66.1.262.103.24
4.244.825.045.30b. !i3
b. 645.72b. 796.196. 56
6. 9b7. 327.537.577.67
7.737.737.677.587.44
7.417.377.237.006.76
6.536.366.286.125.94
5.785.405.285.074.81
4.393.913.503.132.81
2.472.17
c
(mb)
8 . 015.023.033.5
45.053.058.061.06 :1 . O
60. b58.555.553.5b l . b
50.049.048.047.046.0
45.044.543. b43.042.0
41.040.540.039.038.0
37.537.538. 038.539.5
40.542.045.548.049.5
49.547.54b. 543.54 1.5
39. 036.0
PART 1-3 129
THE 3H(d,n)4He REACTION
14.8
14.6
14.4
14.2-
13.8-
13.6-
13.4-
0.07 MeV;
300
100-
20)
1
10
3--r-i-+
(bl
iO.07 MeV
;0.06 MeV
J0.05 MeV
j0.04 MeV
'. i0.02 MeV
0 30 80 90 120 lf)0 1(10
'lab "lab
FIG. 23. (a) Neutron energy values and (b) differential cross-sections for the 3H(d, nflle reaction: 0.02-0.07 MeV.
o7)Oovg.VIO
50
>JO
100
FIG. 24. (a) Neutron energy values and (b) differential cross-sections for the 3H(d, n/4He reaction: 0.08-0.18 MeV.
16-
15.5-
1 5 -
14.5-
13.5-
13
1 2 . 5 -0
( a )
30 60 90' I120 100
220-,
200-
1B0-
CO
0>
a
160-
140-
i 120-
100-
80 -
60 -
40
(fa)
0.20'MeV!
0.25 MeV:
0.30 MeVi
0.35 MeVi
0.40 MeV
:0.45 MeV
to
a73O</>
ovsaVI
O
som
100 30 60 90 120 100 100
FIG. 25. (a) Neutron energy values and (b) differential cross-sections for the 3H(d, njAHe reaction: 0.20-0.45 MeV.
55
16.5-
15.5-
H.5-
13.5-
1S.5-
I 0.5 MeV
100
PSH
F/G. 26. a,/ Neutron energy values and (bj differential cross-sections for the 3H(d, n)*lle reaction: 0.5-1.0 MeV.
19
100
OWO
mjom
r>o iao
. 27. fa Neutron energy values and (bj differential cross-sections for the 3H(d, nflie reaction: 1.1-2.0 MeV.
24
2 2 -
2 0 -
1 2 -
10-
( a )
2.5 McV
30
30 00 90 1K0 lf>0 100
T3
0)
-q io
c33
3- ' I ' ' ' ' ' I '30 00 90
0, .
' I ' ' ' ' ' I 'IfJO l f iO 1(10
5
FIG. 28. (a) Neutron energy values and (bj differential cross-sections for the 3H(d, n)4He reaction: 2.5-6.0 MeV.
i) MeV
10 MeV
B MeV
00 90 120 lf>0 11)030 60 90 120 ifiD 1B0
ON
O
8
o
B
y Ub "lab
FIG. 29. (a) Neutron energy values and (b) differential cross-sections for the 3H(d, n)*He reaction: 7-12 MeV.
1000.6- ~r~r~r
60 90 120 100
FIG. 30. (a) Neutron energy values and (b) differential cross-sections for the 3II(d, n)*lle reaction: 13-20 MeV.
"O
Hi
138 DROSG and SCHWERER
3.4.1. ~'Li(p, no)1Beand1Li(p, n^Be*
Table XII gives the relevant reaction data and Figs 35-40 illustrate theangular dependence of the neutron energies and of the differential cross-sections.Although above Ep = 2.37 MeV (En(0°) = 0.65 MeV) a second neutron line (fromthe 0.43 MeV excitation of 7Be) is present (actually, up to 2.42 MeV there is evena third line), its intensity is less than 10%, so it can be tolerated in some applica-tions. The onset of breakup neutrons at 3.69 MeV (En(0°) = 2.01 MeV) furtherlimits the use of this reaction as a 'monoenergetic' source to neutron energiesbelow 4 MeV. As in the case of d-D breakup, calculated corrections using double-differential cross-sections can be applied [28].
From Fig. V it can be seen that the energy dependence of the 0° cross-sectionis very strong for proton energies below 2.5 MeV (0.8 MeV neutron energy). Inthis region the energy dependence is generally larger than 5% for a 1% change inbeam energy. Therefore, a careful determination of the effective beam energy willoften be necessary when using this reaction.
Single line spectra below En = 121 keV can be obtained at angles >0°. However,in such cases the background from the neutrons at smaller angles (with higherenergy) is troublesome.
The advantages of the p-7Li source are:
(1) Small kinematic energy spread (see Fig. 1). For an opening angle of thesample of ±5° the relative energy resolution caused by the kinematic spreadis close to 0.15% of the neutron energy over the range of interest.
(2) Between 0.4 and 0.7 MeV neutron energy, the yield is higher than for thecompeting p-T reaction. An additional advantage over the p-T reaction is thehigher projectile energy, which gives, e.g. better time resolution in time offlight experiments.
(3) The production of targets for high resolution work is comparatively simple.Usually they consist of lithium metal evaporated on a tantalum [23, 28, 29],silver or tungsten backing. Even natural lithium, which contains 7.5% 6Li, canbe used (the (p, n) threshold of 6Li at 5.92 MeV is outside the useful range ofthe p-7Li reaction). Although the handling of the compound LiF, which isalso used as a target material, is easier, metallic Li is better because its specificneutron yield is three times as large.
3.4.2. lHCLi, n^)1 Be and lH(nLi, n^Be*
If the incoming energy E^ in Tables X and XI is multiplied by a factor of6.9637 and the cm. angle 0 is changed to 180°- 0 , those tables can also be usedto calculate the cross-sections for the 7Li-H reactions.
Table XIII summarizes the relevant reaction data. The special feature of thissource is the containment of the neutrons in a forward cone with a half-angle
Text cont. on p. 158.
PART 1-3 139
THE 2H(t,n)4He REACTION
16
15.5-
1 5 -
14.5-
14
ia.5-
13-
12.5
0.0-1 MeV
0.07 MeV
0.10 MeV
0.17 MeV
30 00 901 I •120
' I 'lf iO
SOO
4> 1 0 0 -
a
X)
10
( b )
; 0.17 MeV;0.23 MeV
; o.io MoV
0.07 MoV
:0.04 MeV
D90OtnO»ao.
r>XtnpaM50
180 0 30 GO 120
0.90
ab lab
FIG. 31. (a) Neutron energy values and (b) differential cross-sections for the 2H(t, n)*He reaction: 0.04-0.40 MeV.
-r-i-i no
o n
19-
18-
1 7 -
<? 16
hf 16-
•
L4-
13-•
12-
•
11-
10-
— ~ .
—i—i—r
^ • • \
^v
\ %* • • . ; • • : \
. T S . . . *
\ \ \
\ '
w- l - > j . • 1 • '
%
\vN
\\y....
' ' 1
\ .
.A
•• i 0.7 McV
\\
; 1.0 McV
• 1.3 MeV
! 2.0 MeV
2.5 MeV
!U)_MeV
•••! " f ^ ^ S
60
uCD
10-
8
2.5 MoV
3.0 MeV
"0
30 0 0 90 120 l!30 100 3 0 60
8,90 120
'lab "lab
FIG. 32. fa) Neutron energy values and (b) differential cross-sections for the 2H(t, n)4He reaction: 0.7-3.0 MeV.
150 100
10
8-100 mo iso 1BO
FIG. 33. (a) Neutron energy values and (bj differential cross-sections for the 2H(l, n)*He reaction: 4-10 MeV.
40-
36
32-
lf)O ino
lab
•0
5
1H0
FIG. 34. (a) Neutron energy values and (b) differential cross-sections for the 2H(t, n)4He reaction: 11-20 MeV.
TABLE XII. Q-VALUES, THRESHOLDS AND NEUTRON ENERGIES AT 0°lab FOR p-7Li
(All energies in MeV)
Exit channel n + 7Be n + 7Be* (0.43) n + 3He + a 7Be** (4.57)
Ein
1.881
1.920
2.372
2.422
3.695
7.110
7.260
Q
En0(0
0.030
0.121
0.650
0.703
2.015
5.450
5.600
cm.)
-1 .644
En0(180°c.m.)
0.030
0.000
-
-
-
En,(0°c.m.)
0.037
0.153
1.556
5.010
5.161
-2.073
Eni(180°c.m.)
0.037
0.000
-
-
En m a x
0.058
3.805
3.958
-3.230
En2(0
0.112
0.460
cm.)
-6.214
En2(180°c,n.)
0.112
0.000
OtooenOind SC
H
w99tn
PART 1-3 145
THE 7Li(p,n)7Be REACTION
0.6-
0.5-
0.4
0.3-
0.2-
0.1-
Z.20 MeVi
12.15 MeV;
!2.05 MeVI
0.0- ' i '110 0(1
1 I '9 0
200
100
r io
Kill
2.15 M<-V
2.20 MeV— -
Z.Z^t McV
a7)oCO
O»
g.VI
n
1(10
(a) Neutron energy values and fb) differential cross-sections for the 1l.i(p, nj^Be reaction: 1.95-2.25 MeV.
0.0
0.8-
0.7-
0.6
0.3-
0.2-
0.1 1 I '30
zoo
100
- aasit
a
c
io
an 00
2.50 Mt-V
2.45 MeV
2.35 M('V
2.40 MfV
120 ino ino IfiO 1(10
FIG. 36. (a) Neutron energy values and (b) differential cross-sections for the nhi(p, npBe reaction: 2.30-2.60 McV.
2.5-
1.5-
2.4
0.5-
4.5
4.0
3.5
3.3
3.0
MeV
MeV
MeV
MeV
MeV
2.7 MeV
1B0
0 0
0 . 4 -
0-
4.5
4J0
3.5
3.3
3.0
2.7
MeV
MeV
MeV
MeV
MeV
MeV
ooo3
a.O
a
F/G. J7. Neutron energy values for the (a) 1Li(p, npBe and (b) 1li(p, n)nBe* reactions: 2.7-4.5 MeV.
60-
b/s
tera
d)
J.ftm
•o
10-
(
— .
1
• . . . ' • • • { • • ' - '
V • •:
/ •\.i
\
V A'
>
; • • • •
) \
* / ;
: • • • •
30
L
»» :
^ ;
V11 !
60 00
\ :
! • • • •
• • 1 ' '
120
• ^ " —
s
: • • • • ;
• • • - > • • • > . . . • _
150 1C
3.3 MeV
3.0 MeVo.v-
4.5 MeV
4.0 MeV
3.5 MeV
3.3 MeV
3.0 MeV
2.7 MeV
150 180
FIG. 38. Differential cross-sections of the fa) 1Li(p, n)nBe and (b) nLi(p, npBe* reactions: 2.7-4.5 MeV.
30 60 90 120 150 160
7.0 MeV
1.6-
6.5
6.0
5.6
5.3
5.0
MeV
MeV
MeV
MeV
MeV
30 60 90 120 150 1801 -,•
7.0
6 ^
6.0
5.6
5.3
5.0
MeV
MeV
MeV
MeV
MeV
MeV
DR
OSG
a
IVIO
mJOmJO
FIG. 39. Neutron energy values for the (a) nLi(p, npBe and (b) nLi(p, nf'Be* reactions: 5.0-7.0 MeV.
70-
ed
cT -b"
•V
B-(
~ x • : :
• • • • • . \ - - - : - - - - : :
• \
" \
. . . %
y.. A. ...: :....., ..A...: :
i. y.
\ vvi• \ • \ \ •
;.V . . M . . t«» : * : \ *
+ | |
\ • ; " V j " " \ < i
\ ! \ \•V \ •\ • \ i
— ; —
r • • • •
; • • • •
\ ]
/
( a ) V /
> 30 60 90
, - r—"-
-
i : ; • • • • ;
• • i • • ' • • I • •
120 150 If
5.3
5.6
6.0
6.5
7.0
MeV_
MeV
MeV
MeV
MeV
MeV
C
10-
1-
ix!
\
- i ^. ..
: ***— r-r-.T— 1
(t
\
I
) )
; ; • • • • • : ; • • • • ;
; ; • • • •
i X ! ! • • • •
.\\;...:.v..:.
:•• V • •
• ; \
1 ' 1
*
J
'•.-•/
w.it
i-^-p^-r-
/ ,
\
— ^ ~
i • • • • •
5.3 MeV
5.6 MeV
6.0 MeV
6.5 MeV
7.0 MeV
30 60 90 120 150 100
FIG. 40. Differential cross-sections oj the (a) 1Lifp, n)1 Be and (bj 1Lilp, nf Be* reactions: 5.0-7.0 MeV.
TABLE XIII. Q-VALUES , THRESHOLDS AND NEUTRON ENERGIES AT 0°,^ FOR 7Li-H(All energies in MeV)
Exit channel
Em
13.095
16.514
25.732
49.509
Q
Eno(O°c
1.439
3.843
8.184
18.803
n+7Be
,m.) En0(180°c.m.)
1.439
0.540
0.254
0.111
-1.644
n+7Be*
Eni(0°.m.)
1.815
7.229
17.975
-2.073
(0.43)
Eni(180°cm.)
1.815
0.457
0.184
n + 3He + a
Enmax
2.828
15.612
-3.230
n + 7Be** (4.57)
En2(0°)
5.439
-6.214
O
)SG
aiid SCH
WE
RE
R
PART 1-3 153
THE 1H(7Li,n)7Be REACTION
0.6-
13.0 MeV
13.B MeV
14.0 MeV
14.2 MeV
14.4 .MeV
14.6 MeV
( a )
30—1
40
2
•sc"
"0
50
\J
-j[
/I ill
5 % / • / / • / • / • •
• • • • : / : / • 7 - i J - • : :
_ ^ / / / ' J i: / : ' /:/ : :: • / . ••/ ;l ; :
X J i /— • ' : / • ; > ' • • .
/ / / •
• i i i T , | . . 1 1
) 10 20 I!
13.0
13.0
14.0
14. a
14.4
1 4 ^
0
Mev : ':
MeV i 1
MeV : :
MeV i 1
MeV
i!eV
( b )
, , i , , . .10 51
oOCO
O
0.
FIG. 41. (a) Neutron energy values and jb) differential cross-sections for the lH(1IA, nj1 Be reaction: 13.6-14.6 MeV.
3.5-
0.5- — I —10 20
— I —30
H . 9 MeV i
15.4 MeV I
15.8 MeV
15.8 MeV
1 — I —40
2000
1000 r 1
•a
I•a
a"
50
100 r . - /
0l.b °l.b
FIG. 42. (a) Neutron energy values and (b) differential cross-sections for the XH(1IA, npBe reaction: 14.9-15.8 MeV.
26 MeV
24 MeV
22 MeV
2 0 MeV
! .B . .M . e .y.17 MeV
' lab
ON
26 MeV
24 MeV
22 MeV
20 MeV
IB MeV_
17 MeV
aoa
I
FIG. 43. Neutron energy values for the la) iH{1Li, n)1Be and (b) 1H(1Li, nf'Be* reactions: 1 7-26 MeV.
1000
13cd
0) 100
10
2 0 0
26MeV
TJ
X
26 MeV
24 MeV
22 MeV
20 MeV
lB_MeV_
17 MeV
FIG. 44. Differential cross-sections oj the (a) *H(nU, npBeand (b) xH(nIA. n)1 Be* reactions: 17-26 MeV.
158 DROSG and SCHWERER
according to formula|(2). However, the second neutron group at 0° (correspond-ing to 180° in cm.) is in most cases not negligible (neither in energy nor in intensity)[30]. Nevertheless, the high yield below En= 1.7 MeV and near 0.6 MeV (from the 180°group), together with the strong forward peaking, makes it a useful source forspecial applications at lower neutron energies. Using double- or triple-charged 7Liions, the necessary incident energy can easily be obtained even with moderateaccelerators. However, the effective beam energy must be determined very care-fully because the cross-section changes rapidly with energy (at 16 MeV, a 1%change of the projectile energy changes the 0° cross-section by more than 50%)Figures 41-44 illustrate the angular dependence of the neutron energies and ofthe differential cross-sections.
Appendix
An interactive Fortran IV program is reproduced here for calculating neutronlaboratory and cm. angles, as well as differential cross-sections and laboratoryneutron energies. Calculation of these quantities is possible at any angle and anyenergy within the ranges covered by the Legendre coefficients given in Tables II,V, VII, X and XI. So and Aj are required as inputs from those tables.
DOUBLE PRECISION WA,WB,WC,WD,OUTRE,MASSDIMENSION MASSI8),0UTREI5),REAIN( 10 1DATA MASS/938.2796434D0,1875.6280461D0,2808. 9*37**600,2808.41413471D0,3727.4094091DO,6534.6662515D0,6533.8864536D0,6634.237251500/DATA REAIN/4H 1H,4H 2H,4H 3H,4H ( P,4H ( D,4H I I,4H 7LI,
21H ,1H ,4H(7LI/NLEG/0/WC/939.b730306D0/NIT/1/DIFF/0./FC/.5/1KI/0/DATA 0UTRE/8H,N ) 3Ht,8H,N ) 4HL:,8H,N )7BE*,1H ,8H,N ) /BE/IC/0./
100 WR1TEI5,!I1 FORMAT!15X,' MONOENERGETIC NEUTRON PRODUCTION'/)WRITE(5,2)
2 FORMAT I' LABEL REACTION BY MASS NUMBERS OF PROJECTILE AND IARGEV )READ!5,3)MNP,MNT
3 FORMAT I 213)MNSUM=MNP+MNTIF (MNSUM .GT. 8) GO TO 100IF (MNP .GT. MNT) NLEG=1IF (MNSUM .NE. 8) GO TO 20WRITEI5.4)
4 FORMAT!' IF BE-7 IS EXCITED, INPUT l'lREADI5,3)IEXCIF IIEXC .EQ. 1) MNSUM=6
6 FORMAT!' LAB CROSS SECTIONS ARE DOUBLE VALUED. ACCESS TO LOW,3' ENERGY GROUP'/' VIA CM ANGLES')
20 WA=MASSIMNP)WB=MASS(MNT)WD=MASSIMNSUM)IF IDABS1WA+WB-WC-WD) .GT. 20.DO) GO TO 100WRITE!5,7 I REAIN!MNT ) ,REAIN(MNP+3),OUTRE(MNSUM-3)
7 FORMATI10X,' NEUTRONS FROM THE REACTION',2A4,A8/)WRITE!1,7) REAIN!MNT ) ,REAIN(MNP+3),OUTRE!MNSUM-3)IF (IWA+WB-WC-WD ) .GT. 0.D0) GOTO 23IF I MNP .GT. MNT) WRITE!5,6)
PART 1-3 159
23 WRITEI5,8 I8 FORMAT!' PROJECTILE ENERGY OR NEGATIVE NEUTRON ENERGY AT 0 D E C ,V IN MEV IREADI5,9)YA
9 FORMAT IF10.5 IIF (MNT .NE. MNP) MNT = 1IF IYA .GT. 0.) GO TO 21TYA=-YAYA=TYA-SNGL(WA+WB-WC-WDI
22 YA=ABS(YA+FCxDIFFICALL RELKIN! YA, WA, WB,WC, Wf:),NIT, TC,MNT ,NLF.G, IKI )D1FF=TYA-TCIF (ABS(DIFF) .LT. 0.00021 GO TO 2.1FC=FC-0.01IF (FC .LT. 0.05) f-C=O.OSGO TO 22
21 NIT=0CALL RELKINIYA,WA,WB,WC,WD,NIT,TC,MNT,NLfc"G,IKI )IF I IKI .EQ. 1) WRITF.11,6)STOPENDSUBROUTINE RELKIN!YA,WA,WB,WC,WD,NIT,TC,MNT,NLEG,IKI )DOUBLE PRECISION PA,EA,RAD,ZC,THC,WA,WB,WC,WD,XXXC,WS,ECDOUBLE PRECISION YC,XCCMIA,XXC,GAMACM,BETACM,BETCCM,tCCM,PCCM,PCDIMENSION TABANGI183)DATA RAD/1.745329252D-2/R0UTE/1./TABANGI l)/0./EA=DBLEIYA)PA=DSQRT(EA**2+2.*EA*WA)EA=DSQRTIPA**2*WAx*2IBETACM=PA/(EA4WB1GAMACM=1./DSQRT(1.-BETACMx«2)WS=(EA+WBI/GAMACMIF (IWS-WD-WC) .LT. 0.1 GO TO 56NANG=1IF (NIT .EQ. 1) GO TO 31
27 WRITEI5.90)90 FORMAT!' NUMBER OF ANGLES, NEGATIVE IF CM.')
READIb,66INANGIF (NANG .GT. 0) ROUTE=0.NANG^IABSINANG)JF (NANG .GT. 181) GO TO 27IF INANG .LT. 1) NANG=1WRITE!b,91)
91 FORMAT!' ANGLES,ONE BY ONE. 1 NEGATIVE VALUE FOR CST.ANG.SPACING' )READ! 5,611DANGDO 34 J=l,NANGIF (J .EQ. 1 ) GO TO 3*1IF 1DANG .Gfc". 0.) GOTO 30TABANGI J) = TABANGIJ-3I-DANGGO TO 3^
30 READ!5,611TABANGIJ)34 IF (TABANG(J) .GT. 180.) TABANGIJ 1=360.-TABANGUI
IF (DANG. GE. 0.) TABANG!1)=0ANGWRITEI1,88) YAWRITEI1,84)EN=YAIF INLEG .tQ. 1) EN=EN*WB/WA
31 ROUSA=ROUTtECCMs(WS*#2+WC**2-WD**2)/(2.*WS)PCCM=DSQRT(ECCM*»2-WC**2)BETCCM=PCCM/ECCMLINES=5DO 53 IA=1,NANGTHC=RAD«TABANGIIA)FACT=0.48
160 DROSG and SCHWERER
39 XCCMIA=DCOSITHCIYC=DSIN(THC)XXC=GAMACM*IXCCMIA+BETACM/BE TCCM)IF !XXC .NE. 0.D0) GOTO 40ANGC=90.GOTO 41
40 XXXC=YC/XXCANGC=SNGLIDATANIXXXCI/RAD)I F (XXC -LT . O.DOI ANGC=ANGC+180.
4 1 I F (ROUTE .GT. 0 . ) GOTO 42DTHAN=ANGC-TABANG(IA)IK lABS(DTHAN) . LEi. 0 . 0011 GO TO 42FACT=FACT-0.01I F (FACT . L T . 0 . 1 ) FACT=0.1THC=THCK( 1 . -!DTHAN/ANGC)*FACT )IF I THC . L T . 3 .141S9265D0) GOTO 39I F (FACT -EQ. 0 . 1 ) THC=O.035898D-5+3.141592654D0IF (FACT .EQ. 0 . 1 ) ROUTE=1.GOTO 39
42 PC=PCCMXDSQRT( YCx*2+XXC**2IKC=DSQKT(PC**2+WC**2ITC=SNGL!EC-WCIIF INIT .EQ. 1) GO TO 57ZC=1.-XXC*PCCM*EC*BETACM/PCx«2SOLC=SNGL(GAMACM*PCCM/PC*ZC)LINES=LINES+1IF (LINES-BO) 50,47,47
47 LINES=0WRITE!1,88) YA
50 ANGCCM=SNGLITHC/RAOIACM=ANGCCMIF (NLEG .EQ. 1) ACM=180.-ACMCALL LCAL(ACM,EN,WQCM,MNT,IA)SOLC=ABS( WQCM/SOLC)WHITE!1,85) ANGC,SOLC,TC,ANGCCM,WQCMROU(E=ROUSAIF (ROUTE .GT. 0.) GO TO 53IF IANGCCM .GT. 180.) IKI=1IF (IKI .EQ. 1) GO TO 57
53 CONTINUEGOTO 57
56 IF INIT. NE. 1) WRITE!1,74)IF (NIT. NE. 1) WRITF.15,74)
57 RETURN61 FORMAT!10F6.2)66 FORMAT!14)74 FORMAT!1HO,15HBELOW THRESHOLD I84 FORMAT!/1H ,7X,'LABORATORY SYSTEM',10X,'CENTER-OF-MASS'
1/1H ,4X,'ANGLE',5X,'CROSS',4X,'ENERGY',5X,'ANGLE',3 5X,'CROSS', /1H ,13X,'SECTION',23X,'SECTION'/)
85 FORMAT!1H , F 1 0 . 2 , 2 F 1 0 . 3 , F 1 0 . 2 , F 1 0 . 3)88 FORMAT I 'OINCIDENT LAB ENERGY' ,F9 .3 I
ENDSUBROUTINE LCAL(ANGCCM,ENIN,WQCM,MN f,IA)DIMENSION PI 64)DATA P/64*0./N/0/IP/0/IF IIA .NE. 1) GOTO 12WRITE!5,48) ENIN
48 FORMAT!' USE ',F6.3,' MEV IN LEGENDRE TABLE'/)10 SUM=0.
WRJTEI5,bOIREAD!5,3) PI324N)WRITE(5,49)
49 FORMAT!' HIGHEST ORDER OF LEGENDRE COEFFICIENTS')READ!5,2)IP1
2 FORMAT! 13)
PART 1-3 161
BO FORMATI' PROJECTILE ENERGY FROM TABLE IN MEV )WRITE!5,99)
99 FORMATI' SIGMA-0' )READI5,3)SKFWRITEI5,5I
5 FORMATI' INPUT OF (REDUCED) PARAMETERS, ONE BY ONE')IF (MNT .NE. 2) MNT=1IF (MNT .EQ. 2) WRITE! 5,4)
4 FORMAT! ' SYMMETRIC IN CM., INPUT OF EVEN PARAMETERS ONLY' )DO 11 I=1,1P1,MNTREAD! 5, 3 I PI 14N)PI I+N)=SKK*PI I+N)
11 SUM=SUM+PII+N)IF IABSISUM/SKF - 1. ) .GT. 0 .002) WRITEI5,51)
51 FORMAT!' CAUTION: CHECK LEGENDRE COEFFICIENTS' I3 FORMATIFlO.b)
IK ( I P 1 .GT. I P ) IP=IP1IF (ABSIENIN-PI32) I .LT. 0 .005) GO TO 12IF (N .EQ. 32) GOTO 13N=32WRITE(5,6)
6 FORMATI ' ADDITIONAL LEGENDRE DATA SET (-OR INTERPOLATION'/)GO TO 10
13 FACT = IENIN-P(32 ) I / I PI 64 I -P I32 ) )DO 1 1 = 1 , IP
1 PI I ) = PI I )+FACT*IP( I+321-PI I I )12 WQCM=0.
XA=1.XM=COSIANGCCM*3.141S93/180. )T=XM+XMDO 87 J=1,IP,MNTXJE=J+1XJ=XJE-1.XLEG=XAXE=IXJ/XJE)*I T*XM*I (XJ+XJEI/IXJ+XJ) I-XA)XA=XMXM=XE
87 WQCM=WQCM+PIJ)*XLEGRETURNEND
ACKNOWLEDGEMENTS
Thanks are due to our colleagues, D.E. Cullen of the Nuclear Data Section,IAEA, and G. Winkler of the Institut fur Radium forschung und Kernphysik, Vienna,for helpful discussions and criticisms, to J.J. Smith of the IAEA Computer Sectionfor his help in implementing the graphics software and to H. Wurz for her effortswith the manuscript.
REFERENCES
[1 ] Fast Neutron Physics (MARION, J.B., FOWLER, J.L., Eds), Interscience, New York (1960).[2] DROSG, M., "Properties of monoenergetic neutron sources from proton reactions with
nuclei other than tritons", Neutron Source Properties (Proc. Consultants Meeting DebrecenHungary, 1980) (OKAMOTO, K., Ed.), IAEA/International Nuclear Data Committee,Vienna, Rep. INDC (NDS>114/GT (1980) 241-264.
[3] UTTLEY, C.A., "Sources of monoenergetic neutrons", Neutron Sources for Basic Physicsand Applications (CIERJACKS, S., Ed.), Pergamon Press, Oxford (1983) 19.
162 DROSG and SCHWERER
[4] DROSG, M., Nucl. Sci. Eng. 67 (1978) 190.[5] DROSG, M., "Production of fast monoenergetic neutrons by charged particle reactions
among the hydrogen isotopes. Source properties, experimental techniques and limitationsof the data", Neutron Source Properties (Proc. Consultants Meeting, Debrecen, Hungary,1980) (OKAMOTO, K., Ed.), IAEA/International Nuclear Data Committee, ViennaRep. INDC (NDS)-114/GT (1980)201 -240.
[6] DROSG, M., Z. Phys. A300 (1981) 315.[7] DROSG, M., "Production of fast neutrons with targets of the hydrogen isotopes. Source
properties and evaluation status of the cross-sections", Neutron Source Properties (Proc.Advisory Group Meeting Leningrad, 1986) (OKAMOTO, K., Ed.), IAEA-TECDOC-410,IAEA, Vienna (1987).
[8] DROSG, M., HAOUAT, G., STOEFFEL, W., DRAKE, D.M., Los Alamos National Lab.,NM, Rep. LA-10444-MS(1985).Germany, 1984.
[9] LISKIEN, H., PAULSEN, A., Nucl. Data Tables 11 (1973) 569.[10] LISKIEN, H., PAULSEN, A., At. Data Nucl. Data Tables 15 (1975) 57.[11 ] KLEIN, H., BREDA, H.J., SIEBERT, B.R.L., Nucl. Instrum. Methods Phys. Res. 193
(1982)635.[12] MARTIN, J.T., SMITH, R.K., Los Alamos Scientific Lab., NM, Rep. LA-6237-MS (1976).[13] MITTAG, S., PILZ, W., SCHMIDT, D., SEELIGER, D., STREIL, T., Kernenergie 22
(1979)237.[14] DROSG, M., AUCHAMPAUGH, G.F., Nucl. Instrum. Methods 140(1977) 515.[15] DROSG, M., AUCHAMPAUGH, G.F., GURULE, F., Los Alamos Scientific Laboratory,
NM, Rep. LA-6459-MS(1976).[16] WAPSTRA, A.H., BOS, K., At. Data Nucl. Data Tables 19 (1977) 177.[17] DROSG, M., VESELY, F., HAOUAT, G., DRAKE, D.M., Verh. Dtsch. Phys. Ges. 19
(1984)922.[18] DROSG, M., et al., Phys. Rev. C 9 (1974) 179.[19] THAMBIDURAI, P., BEYERLE, A.G., GOULD, C.R., Nucl. Instrum. Methods Phys. Res.
196(1982)415.[20] JARMIE, N., BROWN, R.E., Nucl. Instrum. Methods Phys. Res. B10/11 (1985) 405.[21] GRABMAYR, P., RAPAPORT, J., FINLAY, R.W., KULKARNI, V., GRIMES, S.M., in
Nuclear Cross Sections for Technology (Proc. Int. Conf. Knoxville, TN, 1979),US National Bureau of Standards Special Publication 594, US Government PrintingOffice, Washington, DC (1980) 542.
[22] SMITH, D.L., MEADOWS, J.W., Argonne National Lab., IL, Rep. ANL/NDM-9 (1974).[23] MEADOWS, J.W., SMITH, D.L., Argonne National Lab., IL, Rep. ANL/NDM-53 (1980).[24] JARMIE, N., BROWN, R.E., HARDEKOPF, R.A., Phys. Rev. C 29 (1984) 2031.[25] CSIKAI, J., "Production of 14 MeV neutrons by low voltage accelerators", Neutron Source
Properties (Proc. Consultants Meeting Debrecen, Hungary, 1980) (OKAMOTO, K., Ed.),IAEA/International Nuclear Data Committee, Vienna, Rep. INDC (NDS)-114/GT (1980)265-291.
[26] BARSCHALL, H.H., "14 MeV D-T sources", Neutron Sources for Basic Physics andApplications (CIERJACKS, S., Ed.), Pergamon Press, Oxford (1983) 57.
[27] DAVE, J.H., GOULD, C.R., WENDER, S.A., SHAFROTH, S.M., Nucl. Instrum. MethodsPhys. Res. 200(1982)285.
[28] MEADOWS, J.W., SMITH, D.L., Argonne National Lab., IL, Rep. ANL-7938 (1972).[29] MEADOWS, J.W., Argonne National Lab., IL, Rep. ANL/NDM-25 (1977).[30] DROSG, M., Los Alamos Scientific Lab., NM, Rep. LA-8842-MS (1981).
Neutron Source Standards
1-4. THE NEUTRON SPECTRUMOF SPONTANEOUS FISSIONOF CALIFORNIUM-252
W. MANNHARTPhysikalisch-Technische Bundesanstalt,Braunschweig,Federal Republic of Germany
Abstract
THE NEUTRON SPECTRUM OF SPONTANEOUS FISSION OF CALIFORNIUM-252.The spectral distribution of the 2S2Cf neutron spectrum, together with a complete
covariance uncertainty matrix, has been evaluated on the basis of least squares principles.The least squares adjustment was based on experimental data on spectrum averaged neutroncross-sections. The result can be regarded as one of the first steps towards future evaluationsand further experiments. This result is compared with recent data from time of flight experi-ments and with the data of nuclear evaporation theory models.
1. INTRODUCTION
The 2S2Cf neutron field is one of the few which can be realized with onlyminor perturbations of the neutron spectrum. This fact, and its similarity to thetechnically important neutron field of neutron-induced fission in 23SU, is thereason for the importance of the 2S2Cf field in reactor dosimetry and forsurveillance purposes. Its usefulness also extends to other applications, suchas the calibration of neutron detectors. The result has been a recommendationto treat the 2S2Cf neutron spectrum as a standard [1 ]. However, the shape ofthis spectrum has yet to be unambiguously defined, since the data from spectrummeasurements are contradictory even if some convergence of the results has beenrecently observed. While the situation has been reviewed periodically, andrecommendations have been made regarding the shape of the neutronspectrum [2, 3], an improvement in the situation has only been detected since1982 [4]. Recent experiments, using more refined techniques, have givenincreasingly precise results and have diminished the divergence of the data.
In this context, it was considered of interest to use these data for a newevaluation of the 252Cf neutron spectrum [3]. There has also been great demandfor a covariance matrix of the spectrum in order to allow correct propagationof the spectrum uncertainties to the integral parameters determined in reactor
163
164 MANNHART
dosimetry [5]. As discussed in this chapter, there is at present only a very limitedquantity of data that meets the requirements for use in an evaluation of theneutron spectrum with a complete covariance matrix. It is planned to expandthis evaluation in future work and to include other experiments as soon as thecovariances of these data are available. However, this work does not representall of the information available on the 2S2Cf neutron spectrum; it should beregarded instead as the first version of future evaluations.
2. STATUS OF DATA FOR THE NEUTRON SPECTRUM
A complete review of the experiments up to 1979 is given in Ref. [2]. Overthe last five years, much additional effort has been concentrated on carrying outnew experiments [6-15] aimed at resolving discrepancies in the data of thespectrum, found mainly at low (<1 MeV) and at high (>6 MeV) neutron energies.The data available now cover the neutron energy range between 1 keV and28 MeV. Most of the recent experiments have been of a preliminary nature, i.e.the final analyses have not been completed owing to corrections that requireadditional investigation. For these, and all other experiments, detailed uncertaintyanalyses, indispensable in an updated evaluation, are outstanding. It is knownfrom experience that a reanalysis of older experiments aimed at obtaining sufficientdetails of the uncertainty components is a hopeless task; this makes reanalysis ofrecent experiments all the more necessary, while memory of the experimentaldetails is still fresh.
In addition to high resolution time of flight experiments, there is anothergroup of experiments which must be regarded as 'broad' resolution experiments.These experiments, of spectrum averaged cross-section measurements of thresholdand non-threshold neutron reactions, cover various energy ranges in the 2S2Cfneutron spectrum between the limits of a few keV and about 18 MeV. The datacan be determined with a high level of precision, with relative uncertainties of2-3%. A review of all available data is given in Part 2-4. Furthermore,analyses of the uncertainties resulting from experiments carried out since 1979,as well as the covariances generated, are given in Ref. [ 16]. Based on thisinformation, data from the various experiments have been combined by leastsquares techniques (see Part 2-4). This means that the results of spectrumaveraged neutron cross-section measurements are at present the only data setwith a complete covariance matrix containing the full uncertainty informationrequired for evaluations based on the least squares principle.
It should also be mentioned that some progress has recently been made intheoretical calculations of the 2S2Cf neutron spectrum [14, 17-19]. Based onnuclear evaporation theories, results have been obtained which are in good agree-ment with the experimental data. However, sometimes physical parameters ofthe theories which are not sufficiently well known must be adjusted by usingexperimental results.
PART 1-4 165
3. EVALUATION OF THE NEUTRON SPECTRUM BY LEAST SQUARESMETHODS
The aim of an evaluation must be to obtain results which are based as faras possible on objective facts and to avoid subjectivity. This requires consistentattention to all data uncertainties involved in the evaluation process. The onlymethod which meets this requirement is a generalized least squares method.The urgent need of reactor technology to specify results with appropriateuncertainties [20] has led to the use of such methods. A variety of computercodes for these purposes have recently become available, e.g. STAY'SL [21, 22],FERRET [23] and others. All of these evaluation methods are based on the leastsquares principle and combine prior informaiion and experimental data, with fullregard to their uncertainties, with the objective of obtaining results with amaximum likelihood.
The application of this method to the present problem of evaluating the252Cf neutron spectrum has already been described in detail [24]. Only a fewessential points of the procedure are repeated here, the main emphasis being onthe data used in this evaluation.
3.1. Principles of the least squares adjustment
Experimental reaction rates a? of various neutron detectors i, measured inthe 2S2Cf neutron field, are compared with calculations a based on energydependent cross-sections and the 2S2Cf neutron spectrum. Minimization of theX2 gives a minimum value of
v2 — \ \ caO— o W r<jO_ Q \ m
The elements w-- are the components of the weight matrix of the problemexplained below. In the present case, the experimental reaction rates arenormalized by the neutron flux density, i.e. they are spectrum averaged neutroncross-sections:
a9=<a>fxP (2)
The corresponding calculated quantities are
a.=<0>calc = J O1oi(E)X(E)dE (3)
166 MANNHART
The integral of Eq. (3) contains the energy dependent cross-section ofthe neutron reaction i and the normalized spectral flux density distribution of252Cf, with
X(E)dE = 1 (4)
Both of these quantities are parameters of the problem and can be formallywritten as a parameter vector P with an absolute covariance matrix Np, i.e.
P = and N p = (5)
X being the vector of the spectral distribution and 2 the vector of the full setof energy dependent cross-sections involved in the problem.
The evaluation results in a new vector P' and a corresponding matrix Np,which fulfils the minimum condition of Eq. (1). P is often called the problem's'prior information'. P' is then the most likely adjusted value with regard to theprior information and Np is the resulting uncertainty covariance matrix withreduced uncertainties as a result of taking into account the experimentalinformation in Eq. (2). From Eq. (5), it is clear that the spectral distribution,as well as the energy dependent cross-section data, were adjusted, i.e. the zerocorrelation of Np in Eq. (5) vanishes for Np. The result of the adjusted neutronspectrum x' and its covariance matrix Ny is derived from P' and Np . The weightmatrix of Eq. (1) contains the uncertainties of the experimental data ofEq. (2), as well as the uncertainties of the calculated data of Eq. (3). Thematrix is thus an inverse:
(6)
NA contains the covariance matrices Nx and N^ transformed to the calculatedvalues (see Eqs (7) and (10) of Ref. [24]).
3.2. Data on spectrum averaged neutron cross-sections
These data, based on various experiments, have been pre-processed (seePart 2-4). In all, the data from 25 different neutron reactions were used.The reactions and the numerical values of the spectrum averaged cross-sectionsare listed in columns 1 and 2 of Table I. The covariance matrix is shown inthe form of relative standard deviations in column 3 of the table and a correlation
PART 1-4 167
TABLE I. SPECTRUM AVERAGED DATA USED IN THE LEAST SQUARESEVALUATION
React ion
F-19(n ,2n )
Mg-24(n ,p)
A l - 2 7 ( n , p )
A l - 2 7 ( n , c )
T i - 4 6 ( n , p )
T i - 4 8 ( n , p )
Mn-55(n,2n)
F e - 5 4 ( n , p )
F e - 5 6 ( n , p )
N i - 5 8 ( n , p )
N i - 5 8 ( n , 2 n )
Co-59(n,o )
Co-59(n ,2n)
Cu-63(n ,y )
Cu-63(n,a )
Cu-63(n ,2n )
Zn -64 (n ,p )
Z r - 9 0 ( n , 2 n )
I n -115 (n , y )
I n - 1 1 5 ( n , n ' )
Au-197(n ,Y)
U - 2 3 5 ( n , f )
N p - 2 3 7 ( n , f )
U - 2 3 8 ( n , f )
P u - 2 3 9 ( n , f )
a Correlation matrix
1
2
4
1
1
4
4
8
1
1
8
2
4
1
6
1
4
2
1
1
7
1
1
3
1
<o> e x p
(b)
.628E-5
.OO5E-3
.892E-3
.021E-3
.420E-2
.275E-4
.079E-4
.729E-4
.471E-3
.176E-1
.965E-6
-221E-4
.058E-4
.055E-2
.897E-4
-866E-4
.047E-2
.211E-4
.261E-1
.981E-1
.711E-2
.210E+0
.356E+0
-234E-1
.811E+0
in Table I I .
Relativestandarddeviation3
(%)
3.33
2.39
2.16
1.42
1.68
1.81
2.26
1.29
1.73
1.25
3.32
1.78
2.49
3.08
1.88
3.82
1.85
2.78
2.191.31
1.54
1.19
1.65
1.72
1.37
calc
(b)
1.628E-5
2.16OF.-3
5. 140E-3
1.013E-3
1.347E-2
4.096E-4
4.462E-4
8.823E-2
1.415E-3
1.138E-1
8.471E-6
2.164E-4
4.107E-4
9.772E-3
6.767E-4
1.982E-4
3.922E-2
2.058E-4
1 . 2 2 2 E - 1
1.819E-1
7 . 7 2 0 E - 2
1.238E+Q
1.353E+O
3 . 1 3 4 E - 1
1 . 7 9 2 E + 0
Exp/calc
1 . 0 0 0
0 . 9 2 8
0 . 9 5 2
1 . 0 0 8
1 . 0 5 4
1 . 0 4 4
0 . 9 1 4
0 . 9 8 9
1 . 0 3 9
1 . 0 3 4
1 . 0 5 8
1 .027
0 . 9 8 8
1 . 0 8 0
1 . 0 1 9
0 . 9 4 1
1 .032
1 . 0 7 5
1 . 0 3 2
1 . 0 8 9
0 . 9 9 9
0.978
1.003
1.032
1.010
Xpart
0.00
2.62
0.61
0.10
0.16
0.17
0.47
0.17
0.66
0.19
0.72
0.32
0.02
0.37
0.08
2.96
0.13
3. 73
0.470 . 5 2
0.00
1.89
0.00
2.89
0.05
matrix is given in Table II. The data are least squares averages (see Part 2-4)of diverse experiments and it can be seen from Table I that for 15 reactionsthe relative uncertainties are smaller than 2%.
3.3. Prior information on the neutron spectrum
Slightly modified data of a United States National Bureau of Standards(NBS) evaluation of the 2S2Cf neutron spectrum were used as the source of prior
TABLE II. CORRELATION MATRIX OF THE EXPERIMENTAL SPECTRUM AVERAGED NEUTRON CROSS-SECTIONS
C o r r e l a t i o n m a t r i x ( x 1 0 0 )
0 0
F-19(n,2n)Mg-24(n,p)
Al-27(n,p)
Al-27(n,o)
Ti-46(n,p)
Ti-48(n,p)
Mn-55(n,2n)
Fe-54(n,p)
Fe-56(n,p)
Ni-58(n,p)
Ni-58(n,2n)
Co-59(n,a)
Co-59(n,2n)
Cu-63(n,Y)
Cu-63(n,a)
Cu-63(n,2n)
Zn-64(n,p)
Zr-90(n,2n)
ln-115(n,Y )
In-115(n,n')
Au-197(n,1f)
O-235(n,f)
Mp-237(n,f)
U-238(n,f)
Pu-239(n,f)
100
15
8
26
23
21
43
31
21
36
28
36
39
17
24
24
19
35
16
26
23
13
9
8
11
100
27
54
33
30
23
39
35
43
15
28
20
18
25
14
32
19
25
40
35
17
12
10
14
100
44
33
33
25
40
34
44
13
39
22
49
29
43
33
19
31
54
44
19
14
12
16
100
57
50
40
65
57
73
26
49
36
29
42
23
55
32
41
64
59
27
20
17
23
100
64
34
55
46
63
22
42
31
23
35
18
44
27
33
52
48
23
16
14
19
100
30
50
42
56
20
37
28
23
32
18
39
25
33
55
45
22
16
13
18
100
46
32
53
40
58
60
21
36
30
29
50
23
38
33
19
14
12
16
100
56
B5
30
56
42
28
50
22
50
37
39
63
56
35
25
22
30
100
59
21
39
29
23
34
18
43
26
34
53
47
23
17
14
20
100
35
66
49
30
57
24
54
43
43
69
61
35
25
22
30
100
34
36
11
29
17
19
38
16
26
22
13
9
8
11
100
50
23
50
25
37
41
29
46
41
24
17
15
20
100
19
32
28
27
45
21
34
30
17
13
11
15
100
16
36
22
16
22
39
31
13
10
8
11
100
15
31
30
26
44
38
23
17
15
20
100
18
25
17
31
25
11
8
7
9
100
24
31
48
45
21
15
13
10
100
19
31
27
16
11
10
13
100
53
54
19
13
12
16
100
75
32
23
20
2B
100
27
19
17
23
100
67 100
78 67 100
79 66 67 100
>z>so
PART 1-4 169
information [25]. The NBS evaluation covered spectrum measurements up to1974 and parametrized the spectral distribution by a Maxwellian of kT = 1.42 MeV[26]. The deviations of the data from the Maxwellian were taken into accountby five energy dependent, segment correction functions fitted to the data. Theresult was:
X(E) = 0.6672 VEexpC-E/l.42)f(E) (E in MeV) (7)
The correction functions f(E) were linear below 6 MeV and exponential abovethis. The NBS evaluation showed some structure below 0.8 MeV, which is notconfirmed by recent spectrum measurements. The data of Lajtai et al. between25 keV and 1.2 MeV show no deviations from a Maxwellian with kT = 1.42 MeV[15]. This is also confirmed by the data of Blinov et al. taken between 1 keV and1 MeV [8]. The recent data of Batenkov et al. show that between 10 keV and5-6 MeV, no essential deviations from the Maxwellian can be identified [14].Above 6 MeV, the NBS evaluation states a deficit of neutrons compared withthe Maxwellian. This fact has been confirmed by spectrum averaged cross-section measurements of high threshold reactions [27] and also, recently, bydirect spectrum measurements [13]. However, other data exist which contradictthese measurements [6].
Taking all these facts as a basis, it was decided to represent the spectraldistribution by a pure Maxwellian between 0 and 6 MeV and omit the segmentsof the NBS evaluation in this energy range, but include the segment of the NBSevaluation above 6 MeV. After renormalization, the following form was obtained:
X(E) = 0.6680 v/Eexp(-E/l . 42 )g(E) (8)
with
/ 1 for 0 < E < 6 MeVg(E)= I ) (9)
\exp[-0.03(E-6)] for 6 < E < 20 MeV,
Equation (8) assumes that up to 6 MeV, a Maxwellian of kT = 1.42 MeV witha scaling factor of 1.002 is valid and that the spectrum above 6 MeV is describedby another Maxwellian of kT = 1.362 MeV with a scaling factor of 1.126. It iswell known that the Maxwellian is only a rough approach to describe the fissionspectrum in the laboratory system. On the other hand, it is adequate andconvenient for the present purposes.
In all, 30 group averages of Eq. (8) were formed and used in the evaluation.The energy bins were 0.5 MeV between 0 and 10 MeV and 1 MeV between 10and 20 MeV. With these averages Y, Eq. (4) must be rewritten as
30
i = 1
Energy(MeV)
0 -
0.25 -
0.8 -
1.5 -
2.3 -
3.7 -
6.0 -
8.0 -
12.0 -
range
• 0.25
• 0.8
1.5
2.3
• 3.7
6.0
8.0
12.0
•20.0
170 MANNHART
TABLE III. RELATIVE STANDARD DEVIATIONSFROM THE NBS EVALUATION AS DETERMINEDFROM THE SCATTER OF THE EXPERIMENTALDATA
Relative standarddeviations
13.0
1.1
1.8
1.0
2.0
2.1
2.1
8.5
15.0a
a This value is based on an estimate by the author.
The NBS evaluation gave relative standard deviations ( la level) in variousenergy ranges. These are given in Table III. The data contained in this tablewere used in the generation of the covariance matrix of the neutron spectrum.The relative uncertainties of the data in the table are very similar to thoseobtained by attributing a 2% uncertainty to the kT = 1.42 MeV of a Maxwellian[28]. However, taking into account the Maxwellian shape of Eq. (8) wouldresult in full correlations between all of the data in Table III in the case of anon-normalized spectrum, or full correlations and anticorrelations for anormalized spectrum. These rigid conclusions hamper any adjustment procedurein obtaining sufficiently detailed results, as they indicate a pure shape adjustment(by a scale factor) of the spectrum over the whole energy range in the non-normalized case (for a normalized spectrum the shape adjustment factor runsin opposite directions below and above the average energy of the Maxwellian).The implicit inclusion of the Maxwellian shape in the covariance matrix wastherefore avoided.
After the generation of a union group structure [24] containing the energydelimiters of the data in Table III, as well as those of the groups of Eq. (10),all diagonal elements of the union group matrix were filled with the correspondinguncertainties of the data in Table III, which meant that these uncertainties wereregarded as belonging to a non-normalized spectrum. All data between one of
PART 1-4 171
the energy ranges in Table III were assumed to be equally correlated by 75%.No correlations between the different energy ranges were used. A correlationcoefficient of 1.00 for one of the energy ranges in Table III would mean thatthe whole range would be adjusted by the same factor, whereas a correlationcoefficient of 0.50 would surely underestimate the Maxwellian-type structurein the range. A correlation coefficient of 0.75 was therefore chosen. Thisprocedure is a compromise which takes account of the lack of detailed information.It avoids fixing the adjustment procedure on a Maxwellian shape, but it takesinto account the fact that the data of a segment of the NBS evaluation must atleast be correlated owing to the fitting functions.
The union group matrix was then collapsed to the final group structure ofthe evaluation. Up to this point, it was not taken into account that the neutronspectrum can be normalized according to Eqs (4) and (10). However, thiswas now done by a transformation of the matrix from the non-normalized tothe normalized case, as shown in Eqs (17) and (18) of Ref. [24]. The adjustmentof the neutron spectrum in a certain energy group can now be compensated forin other groups with a full conservation of the normalization. This is automaticallytaken into account owing to the special structure of the absolute covariancematrix of the normalized spectral distribution, with the sum over each row andover each column of the matrix being equal to zero.
3.4. Energy dependent cross-section data
Most of the cross-sections of the reactions listed in Table I were takenfrom the Evaluated Neutron Data File/B-V (ENDF/B-V). For the 24Mg(n,p),s4Zn(n,p), 90Zr(n,2n) and 63Cu(n,2n) reactions, the data are taken from Ref. [29],while Ref. [30] is the source for 19F(n,2n). The ENDF/B-V data on the27Al(n,a), 63Cu(n,a) and S8Ni(n,2n) reactions have been replaced with morerecent data. For 27Al(n,a), the data are from Ref. [31 ], for 63Cu(n,a) fromRef. [32] and for 58Ni(n,2n) from Refs [33] and [34].
The original point-wise data on the energy dependent cross-sections aretransformed to group cross-sections according to the structure of Eq. (10).The data are then weighted with the spectral distributions of Eqs (8) and (9),resulting in an exact identity of the integral of Eq. (3) with the sum over thegroup constants of the cross-sections a and of the spectral distribution x, with
30
oi(E)X(E)dE = ^ <7/Xj (11)
0 j = 1
J
Thus the usual problem of the group sums forming the integral only in a firstapproximation is avoided. The covariance matrices of the energy dependent
172 MANNHART
cross-sections have been taken from the literature (i.e. from ENDF/B-V and fromreferences already mentioned). These matrices, showing their own groupstructures, have been transformed to the group structure of the present problemaccording to the rules given in detail in Refs [24] and [35].
For the neutron reactions considered here, the ENDF/B-V covariance fileshows a cross-correlation only between the 23SU(n,f) and 239Pu(n,f) reactions.For all other reactions, no cross correlations were stated. It is well known thatthis is far removed from experimental reality (see, for example, Refs [36-38]).However, owing to the lack of data, the covariance matrix of the whole set ofenergy dependent cross-sections generated here shows no such cross correlations.Consequently, the 23sU(n,f) to 239Pu(n,f) correlations have been neglected as aresult of the consistency between the other reactions, i.e. the present covariancematrix contains only correlations between data belonging to the same reaction.
4. RESULTS OF THE EVALUATION OF THE SPECTRAL DISTRIBUTION
Before the least squares adjustment was performed, the minimum valueof x2 in Eq. (1) was calculated. This quantity is a measure of the consistencyof the experimental data (Section 3.2) with the prior information on the spectraldistribution and on the energy dependent cross-section data used. This consistencytest takes the uncertainties of all these data fully into account. An evaluation canonly be justified when this consistency test is positive.
With the present data a minimum x2 of 19.3 was obtained, which should beconsidered at 25 degrees of freedom. The result indicates that an adequateconsistency was given. The calculated spectrum averaged cross-sections ofEq. (1) are shown in column 4 of Table I. In addition, the ratio of theexperiment to the calculation that was formed is given in column 5 of that table.In the last column of the table, the partial components XPart of the minimumX2 belonging to the various reactions are given. These values were obtained byperforming only the second summation in Eq. (1). The data should not bemistaken for individual x2 calculated without regard to the other reactions.The data of Xpart are of some use in identifying problems between the experimentand the calculation. Values exceeding unity indicate the probability of suchproblems. Here, this is true of the 24Mg(n,p), 63Cu(n,2n), 90Zr(n,2n), 235U(n,f)and 238U(n,f) reactions. Within their uncertainties the experiment and thecalculation disagree. These inconsistencies are not new and were already quotedfor 23SU and 238U in Ref. [5] and for 24Mg, 63Cu and 90Zr in Fig. 5 of Ref. [39].In all cases the inconsistency is not large enough to justify a rejection of the data.From the last two columns of Table I it can also be seen that an exp/calcvalue strongly deviating from unity does not automatically result in a largecontribution to the x2 •
The inputs and outputs of the evaluation are listed in Table IV. The energydelimiters of the group structure are listed in the first two columns of this table.
PART 1-4 173
TABLE IV. INPUTS AND OUTPUTS OF THE EVALUATION OF THESPECTRAL DISTRIBUTION
(MeV)
0 . 0
0 . 5
1 .0
1 .5
2 . 0
2 . 5
3 . 0
3 . 5
4 . 0
4. 5
5 . 0
5 . 5
6 . 0
6 . 5
7 . 0
7 . 5
8 . 0
8 . 5
9 . 0
9 . 5
10.0
11.0
12.0
13.0
14.0
15.0
16.0
17.0
18.0
19.0
Eu
( M e V )
0 .5
1 .0
1. 5
2 . 0
2 . 5
3 . 0
3 . 5
4 . 0
4 . 5
5 . 0
5 . 5
6 . 0
6 . 5
7 . 0
7 . 5
8 . 0
8 . 5
9 . 0
9. 5
10.0
11 .0
12.0
13.0
14.0
15.0
16.0
17.0
18.0
19.0
20.0
1
1
1
1
1
8
6
4
3
2
1
1
1
7
5
3
2
1
1
9
1
5
2
1
7
3
1
8
4
2
X.in
. 280E-1
.689E-1
.545E-1
-288E-1
.029E-1
.003E-2
.121E-2
.625E-2
.464E-2
.575E-2
.904E-2
.402E-2
.O2OE-2
.347E-3
.275E-3
.778E-3
.701E-3
.927E-3
.372E-3
.761E-4
.185E-3
.954E-4
.979E-4
.486E-4
.392E-5
.668E-5
.816E-5
.978E-6
.430E-6
.183E-6
Relativestandarddeviation
(%)
4 . 5 1
1.03
1.65
1.21
1.05
1.86
1.87
1.40
2 .09
2 .09
2 . 10
2 .10
2 .24
2 .25
2 . 2 5
2 . 2 5
8 .49
8 .49
8. 49
8 .49
8 .49
8 .49
15.02
15.02
15.02
15.02
15.02
15.02
15.02
15.02
Xout
1.253E-1
1.691E-1
1.544E-1
1.294E-1
1.034E-1
8.056E-2
6. 160E-2
4.650E-2
3.480E-2
2.587E-2
1.913E-2
1.408E-2
1.025E-2
7.376E-3
5.296E-3
3.793E-3
2.675E-3
1.912E-3
1.363E-3
9.695E-4
1.177E-3
5.863E-4
2.839E-4
1.502E-4
7.663E-5
3.790E-5
1.860E-5
9.150E-6
4.503E-6
2.215E-6
Relativestandarddeviationa
(%)
3.79
1.01
1.63
1.16
0 .95
1.75
1.76
1.25
1 .95
1.96
1.96
1.97
2 .15
2 .15
2 .15
2 .15
5.32
5. 37
5.46
5.53
5.39
5.60
7.40
6.39
6.48
7.07
7.64
7.97
8.15
8.24
a Correlation matrix given in Table V.
174 MANNHART
XoUT
XlN
no
105
100
0.95
090
• T
:J1J•jjIliUll]itlTi1ilil]
1 ! 1 1 1
71. 1 .
!
(I
1
_— "L
I
.
|
*-• —
-
-
8 10 12En[MeV)
U 16 20
FIG. 1. Ratio of the output to the input for the evaluation of the spectral distributionof2S2Cf.
The averages of the spectral distributions of Eqs (8) and (9), and theiruncertainties, are listed in columns 3 and 4. The relative standard deviationsshown in column 4 are those obtained after the collapse of the group and afterthe normalization of the input covariance matrix. This explains the deviationsbetween 0 and 4 MeV compared with the data in Table III. The adjusted spectraldistribution and its uncertainty are given in the last two columns of Table IV.It can be seen that an essential uncertainty reduction was obtained for thespectrum data above 8 MeV.
The ratio of the output of the evaluation relative to the input is shown inFig. 1. The error bars quoted correspond to the uncertainties of the outputdata. The figure shows that within the uncertainties the adjusted spectraldistribution is fully consistent with the prior information. Between 0.5 and8 MeV the maximum deviation from Eq. (8) is 0.6%. However, too high avalue should not be placed on the remaining structures, especially at high neutronenergies. Obviously, a part of this structure is due to the missing cross correlationsbetween the various energy dependent cross-section data sets. It should also bementioned that not more than 0.93% of the total spectrum intensity is above8 MeV and only 0.06% is above 12 MeV of neutron energy.
The absolute covariance matrix of the input spectrum Nx takes into accountthe normalization of x- As shown in Ref. [24], this results automatically in an
PART 1-4 175
output covariance matrix N^ which also fulfils the normalization condition. Thecorrelation matrix of the adjusted spectral distribution shown in Table V there-fore gives correlations as well as anticorrelations. The data in this table show thatthe ranges of maximum intensity of the spectral distribution are only weaklycorrelated with the low intensity ranges at high neutron energies. Between 4 and8 MeV the correlation pattern is only slightly modified owing to the experimentaldata, whereas below 4 MeV and above 8 MeV the experimental data essentiallychange the structure of the correlations as compared with the prior information.
Finally, it should be mentioned that the reconstruction of the absolutecovariance matrix of the spectral distribution from the data given in Tables IVand V can (owing to rounding errors) result in a matrix which does not fullytake into account the normalization. This can be circumvented by applyingEq. (17) in Ref. [24] to the matrix. With this procedure the matrix remainsunchanged if it already corresponds to the normalized spectrum: otherwise thenormalization will be regenerated.
5. COMPARISON WITH OTHER EXPERIMENTAL AND THEORETICALDATA
The aim of this work was to obtain a result with a complete uncertaintydescription. As mentioned earlier, this resulted in a strong limitation of thedatabase available. To get an impression of the adequacy of the present data,some of the latest experimental and theoretical data are compared in Figs 2-4.
The approximation of the 2S2Cf neutron spectrum of Eqs (8) and (9) iscompared with the results of two nuclear evaporation models. In the modelcalculations of Madland and Nix [40] and Madland et al. [41], a remaining freeparameter, the level density parameter, has been adjusted with regard to theexperimental data of Poenitz and Tamura [10]. This adjustment has been madein the neutron energy range between 0.225 and 9.8 MeV, the energy range coveredby the experiment. The other theoretical description, by Marten andSeeliger [42, 43] using a complex cascade evaporation model (CEM), takes intoaccount that the emission of neutrons is not isotropic in the centre of masssystem of the fission fragments due to the fragment spin. A 10% anisotropyis involved in the calculation. In contrast to the Madland and Nix model, theCEM model has no free parameter. Both models differ substantially below0.5 MeV and above 10 MeV neutron energy.
The experimental data used in the comparison are taken from Lajtai et al.between 25 keV and 1.2 MeV [15], Blinov et al. between 42 keV and 11.4 MeV[44] and Marten et al. between 8.9 and 19.8 MeV [45]. The data are plotted inFigs 2-4 in the form of ratios, relative to a Maxwellian with kT = 1.42 MeV.
The experimental as well as the theoretical data show a clear deviation fromthe Maxwellian, with kT = 1.42 MeV above about 6 MeV neutron energy. This
TABLE V. CORRELATION MATRIX OF THE EVALUATED SPECTRAL DISTRIBUTION x o u t
Energy range Correlation matrix (xlOO)(HeV)
100
-57 100
-4B 44 100
-44 19 -3 100
-53 6 -15 57 100
-29 -17 -20 -11 40 100
-29 -16 -19 -10 41 68 100
-36 -10 -19 -4 18 27 27 100
0.0
0.5
1.0
1 .5
2.0
2.5
3.0
3.5
4.0
1.5
5.0
5.5
6.0
6.5
7.0
7.5
8.0
8.5
9.0
9.5
10
11
12
13
14
15
16
17
18
19
- 0.5- 1.0
- 1.5
- 2.0
- 2.5
- 3.0
- 3.5
- 4.0
- 4.5
- 5.0
- 5.5
- 6.0
- 6.5
- 7.0
- 7.5
- B.O
- 8.5
- 9.0
- 9.5
- 10
- 11
- 12
- 13
- 14
- 15
- 16
- 17
- 18
- 19
- 20
-20
-20
-20
-20
-18
-18
-18
-18
7
6
£
1
1
1
0
0
0
0
0
-3
-2
-2
- 2
13
13
13
13
-6
-6
_
_
-1
-1
-1
-1
-0
-0
-0
-0
-9
-9
-9
-9
1
1
1
1
-3
-3
_ 3
_ i
-i
-i
-i
-1
-i
-i
-i
-i
i
i
2
2
15
16
16
16
-6
-6
_
_
-0
-0
-0
-0
-0
0
0
0
-11
-10
-9
-9
10
10
11
11
-6
-6
- 5
-i
-i
-i
-0
-0
-0
-0
-0
-19
-18
-18
-17
-4
-4
-4
-I)
-2
-2
_ |
_ J_ 1
-0
-1
-1
-0
-0
-0
-0
-0
-IB-IB
-17
-17
-4
-3
-3
-3
-2
-2
1
_ 1
- 1-0-1
-0
-0
-0
-0
-0
-0
53
54
54
54
-2
-2
-1
-1
-4
-4
_ -i
_ 3
- 3
00
0
0
0
0
0
0
100
72
72
72
-1
-0
-0
-0
-3
-3
- 3
_ j
- 3
i
i
i
i
i
i
i
i
100
72
72
-0
-0
-0
0
-3
-3
_ 5
_ j
- >i
i
Ii
i
i
i
i
100
72
-0
-0
0
0
-4
-3
- 3
j
_ -i
i
i
i
i
i
i
i
i
100
-0
-0
0
0
-4
-3
_ J
_ y
- 3
i
i
i
i
i
i
i
i
100
76
76
76
-20
-19
-18
-19
-17
i
i
i
i
i
i
i
i
100
76
76
-20
-20
- 1 8
-1 9
-1 8i
i
i
i
i
i
i
i
100
76
-21
-20
-19
-19
- 19
- 18
1
1
1
1
1
1
1
1
100
-21
-20
19
1 9
20
1 8
1
1
1
1
1
1
1
1
100
36
37
38
36
38
-5
2
4
3
2
2
2
1
100
37
38
37
39
-5
2
4
3
2
2
1
1
1Q0
39
38
40
-5
2
4
3
2
2
1
1
100
39
4 1
-5
2
3
3
2
2
1
1
100
39
-5
2
4
3
2
2
1
1
10 0
-8
-0
3
2
1
1
0
0
100
-17
-6
3
7
10
12
12
100
-26
-15
-6
-2
0
2
100
-14
-5
-0
2
4
100
2 100
6 12 100
9 14 17 100
10 15 17 19 100
sz5!33JO
PART 1-4 177
1.2
1.1
3 1.0
0.9
0.8
0.7
i ilkl ift •
p i *HiIpP
ifI
0.01 0.02 0.05 0.10 0.20
E (MeV)
0.50 2.00
FIG. 2. Various representations of the 2S2Cf neutron spectrum relative to a referenceMaxwellian, with kT = 1.42 MeV. The solid curve denotes the spectrum of Eqs (8) and (9).The dashed curve represents the theoretical calculations ofMadland and Nix [40] andMadland et al. [41 ]. The dot-dashed curve represents the calculations of Marten andSeeliger [42, 43], with (3 = 0.1. The experimental data (triangles) are from Lajtai et al. [15].
0.01 0.02 0.05 0.10 0.20
E (MeV)
0.50 MeV 2.00
FIG. 3. Same details as for Fig. 2. The experimental data (circles) are from Blinov et al.[44].
178 MANNHART
18 MeV 20
FIG. 4. Same details as for Fig. 2, except that the neutron energy range is from 2 to 20 MeV.The experimental data above 2 MeV are from Blinov et al. [44] (circles) and from Marten et al.[45 ] (squares).
effect seems to be best described by the theory of Marten and Seeliger [42, 43](dot-dashed curve). The formula for Eqs (8) and (9) (solid curve) under-estimates the effect, whereas the theoretical data of Madland and Nix andMadland et al. (dashed curve) show an overestimation. Between 1 MeV and4 MeV, the experimental data show a slight enhancement relative to the referenceMaxwellian. This effect is well described by both evaporation theories. Below1 MeV neutron energy, the experimental data strongly support the referenceMaxwellian of kT = 1.42 MeV. Below 0.5 MeV, the data of both evaporationtheories diverge. The theoretical data of Marten and Seeliger are compatiblewith the experimental data available. The same is not true of the theory ofMadland and Nix and Madland et al. This is easily understandable, since thelatters' theory has been optimized between 0.2 and 10 MeV owing to the adjust-ment of their data to the data of Poenitz and Tamura [10]. The logical conse-quence is that their theory must have some deficiencies outside of the range ofadjustment, i.e. their data are restricted in validity below 0.2 MeV and above10 MeV.
The data of both evaporation theories are listed numerically in Tables VIand VII. They are given between 1 keV and 20 MeV. For both theoreticalcalculations no original uncertainty information is available. Thus, the plots ofFigs 2-4 must be used to obtain some rough estimates of the accuracy ofthese calculations.
PART 1-4 179
TABLE VI. NUMERICAL DATA FROM THE THEORY OF MADLAND et al.ON THE 252Cf NEUTRON SPECTRUM [40, 41 ](Data from Los Alamos National Laboratory; applicable energy range: 1 keV to20 MeV; interpolation: In (N(E)), linear in E)
E(MEV)
1.O0E-31.30E-31.6OE-31.90E-32.20E-32.50E-32.8OE-33.1OE-33.40E-33.70E-34.OOE-34.3OE-34.S0E-34.90E-35.2OE-35.50E-3S.SOE-36.1OE-36.40E-36.70E-37.OOE-37.3OE-37.60E-37.90E-3S.20E-38.50E-38.80E-39.10E-39.40E-39.70E-3l.OGE-21.3OE-21.60E-21.90E-22.20E-22.5OE-22.SOE-23.1OE-23.40E-23.7OE-24.OOE-24.3OE-24.60E-24.90E-25.2OE-25.50E-25.8OE-2
N(E)(1/MEV)
1.750E-21.995E-22.213E-22.411E-22.595E-22.766E-22.927E-23.079E-23.224E-23.363E-23.4S7E-23.625E-23.749E-23.869E-23.985E-24.098E-24.208E-24.315E-24.419E-24.521E-24.621E-24.718E-24.814E-24.908E-24.999E-25.O9OE-2S.178E-25.2S5E-25.351E-25.435E-25.518E-2S.285E-26.966E-27.583E-28.152E-28.681E-29.178E-29.648E-21.009E-11.052E-11.093E-11.132E-11.169E-11.206E-11.241E-11.275E-11.308E-1
E(MEV>
1.1OE-31.40E-31.70E-32.OOE-32.30E-32.SOE-32.9OE-33.20E-33.5OE-33.8OE-34.10E-34.40E-34.70E-35.OOE-35.30E-35.60E-35.90E-36.20E-36.50E-36.80E-37.10E-37.40E-37.70E-38.00E-38.30E-38.60E-38.90E-39.20E-39.50E-33.80E-31.1OE-21.40E-21.70E-22.OOE-22.30E-22.6OE-22.9OE-23.20E-23.50E-23.8OE-24.1OE-24.40E-24.70E-25.00E-25.30E-25.60E-2S.9OE-2
N<E>(1/MEV)
1.835E-22.070E-22.281E-22.474E-22.653E-22.82OE-22.978E-23.128E-23.27iE-23.408E-23.540E-23.667E-23.789E-23.9OSE-24.023E-24.135E-24.244E-24.350E-24.454E-24.S55E-24.654E-24.7S0E-24.845E-24.93SE-2S.O3OE-2S.119E-25.2O7E-25.294E-25.379E-25.463E-25.785E-26.S20E-27.178E-27.777E-28.332E-28.850E-29.337E-29.799E-21.O24E-11.O66E-11.106E-11.144E-11.182E-11.217E-11.252E-11.286E-11.319E-1
E(MEV)
1.20E-31.50E-31.SOE-32.1OE-32.40E-32.70E-33.00E-33.30E-33.6OE-33.9OE-34.2OE-34.5OE-34.80E-35.1OE-35.4OE-3S.70E-36.00E-36.3OE-36.6OE-36.9OE-37.2OE-37.50E-37.80E-38.10E-38.4OE-38.7OE-39.OOE-39.3OE-39.60E-39.90E-31.2OE-21.5OE-21.80E-22.1OE-22.40E-22.7OE-23.00E-23.3OE-23.6OE-23.9OE-24.20E-24.50E-24.80E-25.10E-25.40E-25.70E-26.OOE-2
N<E>(1/MEV)
1.917E-22.143E-22.347E-22.535E-22.710E-22.874E-23.029E-23.177E-23.318E-23.453E-23.583E-23.708E-23.829E-23.947E-24.061E-24.172E-24.280E-24.385E-24.488E-24.S88E-24.686E-24.782E-24.877E-24.9S9E-25.O6OE-25.149E-25.236E-25.322E-25.4O7E-25.490E-26.040E-26.747E-27.383E-27.967E-28.509E-29.016E-29.494E-29.947E-21.038E-11.079E-11.119E-11.157E-11.194E-11.229E-11.264E-11.297E-11.329E-1
180 MANNHART
TABLE VI (cont.)
E(MEV)
6. 10E-26.40E-2S.70E-27.OOE-27.3OE-27.6OE-27.90E-28.20E-2S.SOE-2s.aoE-29.1OE-29.40E-29.7OE-21.00E-11.3OE-11 .t.OE-11 .9OE-12.20E-12.5OE-12.80E-13.1OE-13.4OE-13.7OE-X4.OOE-14.30E-14.60E-14.90E-15.20E-15.50E-1S.80E-16.10E-16.40E-16.7OE-17.00E-17.3OE-17.60E-17.9OE-18.2OE-18.5OE-18.80E-19.1OE-19.40E-19.70E-11 .OOE+O1.3GE+01 .60E+01.90E+02.2OE+O2.50E+02.80E+03.10E+03.4OE+O
NiE>Cl/MEV)
1.34OE-11.371E-11.401E-11.431E-11.460E-11.488E-11.515E-1i.542E-11.S63E-11-S34E-11.620E-11.&44E-11.S69E-11.692E-11.9O9E-12.095E-12.257E-12.400E-12.528E-12.642E-12.744E-12.836E-12.918E-12.991E-13.05SE-13.113E-13.163E-13.204E-13.239E-13.268E-13.291E-13.308E-13.320E-13.328E-13.334E-13.336E-13.336E-13.333E-13.329E-13.322E-13.314E-13.304E-13.292E-13.279E-13.O87E-12.827E-12.525E-12.211E-11.906E-11.S25E-11.374E-11.1S6E-1
ECMEV)
S.20E-26.50E-26.80E-27.10E-27.40E-27.7OE-28.00E-28.30E-28.60E-28.90E-29.2OE-29.SOE-29.80E-21.1OE-11.40E-11.70E-12.00E-12.3OE-12.60E-12.90E-13.20E-13.5OE-13.80E-14.10E-14.40E-14.70E-15.00E-15.30E-15.60E-15.90E-16.20E-16.50E-16.SOE-17.10E-17.40E-17.7OE-18.00E-18.30E-18.60E-18.90E-19.20E-19.50E-19.80E-11.1OE+O1.40E+01.70E+02.OOE+O2.30E+02.60E+02.9OE+O3.20E+03.SOE+O
H < E)(i/MEV)
1.350E-11.381E-11.411E-11.441E-11.4S9E-11.497E-11.524E-11.SS1E-11.577E-11.603E-11.628E-11.653E-11.S77E-11.769E-11.974E-12.151E-12.307E-12.444E-12.567E-12.677E-12.77SE-12.864E-12.943E-13.013E-13.076E-13.131E-13.178E-13.217E-13.249E-13.276E-13.297E-13.312E-13.323E-13.33OE-13.335E-13.336E-13.335E-13.332E-13.327E-13.319E-13.311E-13.300E-13.288E-13.225E-13.006E-12.729E-12.421E-12.107E-11.809E-11.538E-11.298E-11.090E-1
E<MEV)
6.30E-26.S0E-26.90E-27.20E-27.50E-27.80E-28.10E-28.40E-28.70E-29.00E-29.30E-29.60E-29.9OE-21.20E-1l.SOE-11.80E-12.1OE-12.40E-12.70E-13.00E-13.30E-13.60E-13.90E-14.20E-14.50E-14.80E-15.10E-15.40E-15.70E-16.00E-16.30E-16.60E-1S.90E-17.20E-17.50E-17.80E-18.10E-18.40E-18.70E-19.00E-19.30E-19.60E-19.90E-11.20E+01.50E+01.80E+02.10E+02.40E+02.70E+03.OOE+O3.3OE+O3.60E+0
N(E>Cl/MEV)
1.3S1E-11.391E-11.421E-11.450E-11.479E-11.5O6E-11.533E-X1.S60E-11.586E-11.611E-11.636E-11.661E-11.6S5E-11.841E-12.O36E-12.2O5E-12.354E-12.487E-12.6O5E-12.711E-12.807E-12.892E-12.967E-13.O3SE-13.095E-13.147E-13.192E-13.228E-13.259E-13.284E-13.3O3E-13.316E-13.326E-13.332E-13.336E-13.336E-13.334E-13.330E-13.324E-13.317E-13.3O7E-13.296E-13.283E-13.160E-12.919E-12.S28E-12.315E-12.OO5E-11.715E-11.454E-11.225E-11.O28E-1
PART 1-4 181
TABLE VI (cont.)
E(MEV)
3.7OE+O4.OOE+O4.30E+04.60E+04.90E+05.20E+0S.50E+0S.SOE+G6.iOE+06.40E+06.70E+07.00E+07.30E+07.60E+07.90E-I-0S.20E+08.5GE+08.B0E1-09.IOE+09.40E+O9.70E+0l.OOE+11.3OE+11.60E+11.90E+1
N(E>( 1 /MEV)
9.S89E-2S.094E-26.745E-2S.607E-24.S50E-23.847E-23.176E-22.61SE-22.149E-21.7S2E-21.442E-21.178E-29.610E-37.831E-36.375E-35.iS5E-34.214E-33.422E-32.777E-32.2S2E-31.S25E-31.477E-31.716E-41.893E-52.019E-6
E(MEV)
3.80E+04.IOE+04.40E+04.70E+05.00E+05.30E+05.60E+05.90E+06.20E+06.50E+06.80E+07.XOE+O7.40E+07.70E+0S.OOE+OS.3OE+O8.60E+08.9OE+O9.20E+09.50E+09.80E+01.1OE+11.40E+11.70E+12.00E+1
N(E)(1/MEV)
9.128E-27.S19E-2b.344E-25.269E-24.3S7E-23.61OE-22.977E-22.4SOE-22.011E-21.648E-21.34SE-21.101E-28.977E-37.313E-35.952E-34.839E-33.932E-33.192E-32.530E-32.100E-31.701E-37.265E-48.266E-59.006E-69.522E-7
E(MEV)
3.90E+04.20E+04.50E+04.80E+05.IOE+05.40E+05.70E+06.00E+06.30E+06.60E+06.90E+07.2OE+O7.50E+07.80E+08.IOE+08.40E+08.70E+09.00E+09.30E+09.S0E+O9.90E+01.20E+11.50E+11.80E+1
N(E)(1/MEV)
8.597E-27.169E-2S.965E-24.951E-24.099E-23.386E-22.791E-22.29SE-21.883E-21.542E-21.260E-21.029E-28.385E-36.828E-35.556E-34.516E-33.669E-32.978E-32.415E-31.958E-31.585E-33.543E-43.963E-54.271E-6
TABLE VII. NUMERICAL DATA FROM THE THEORY OF MARTEN ANDSEELIGER ON THE 252Cf NEUTRON SPECTRUM [42, 43](Data from the Technical University of Dresden, German Democratic Republic;
applicable energy range: 1 keV to 20MeV; interpolation: In (N(E)), linear in E)
E(MEV)
N (£)(1/MEV)
l.OOE-3 2.G32E-22.5CE-3 3.2iiE-24.00E-3 4.0S8E-26.OOE--3 4.964E-29.00E-3 6.068E-21.20E-:1 .50E-;2.00E-;2.60E-;3.3OE-J
.' 6.994E-2: 7.805E-2; 8.984E-2
• 1.O2OH-12 1.144E-1
4.30E-2 1.298E-i
£(MEV)
1.S0E-33.OOE-34.5OE-37.00E-3l.OOE-21.30E-21.6OE-22.2OE-22.80E-23.7OE-24.70E-2
N(E)(1/MEV)
2.489E-23.SlfaE-24.303E-25.35SE-26.393E-27.275E-2S.056E-29.410E-21.056E-11.209E-11.354E-1
E( MEV)
2.00E-33.5OE-35.OOE-3B.OOE-31.10E-21.4OE-21.8OE-22.40E-23.OOE-24.00E-25.00E-2
N(E>(1/MEV)
2.873E-23.797E-24.534E-2S.725E-26.700E-27.545E-28.533E-29.816E-21.093E-11.254E-11.393E-1
182 MANNHART
TABLE VII (cont.)
E(MEV) 1/MEV>
E(MEV>
N(E)(1/M£V>
E(MEV)
N(E)(1/MEV)
S.3OE-26.50E-2d.OOE-29.50E-21.20E-11.50E-12.0GE-12.DOE-1
3.30E--14.30E-15.30E-16.S0E-1a.OOE-19.S0E-11.iOE+O1.50E+02.00E+02.60E+03.30E+04.30E+05.30E+0&.50E+08.00E+09.S0E+G1 . 20EH1.50E+12.OOE+1
1.432E-11.573E-11.728E-11.86SE-12.062E-12.260E-12.523E-12.763E-12.967E-13.161E-13.276E-13.344E--13.353E-13.304E-13.149E-12.S83E-12.370E-11.777E-11.213E-16.676E-23.541E-21.609E-25.864E-32.110E-33.S06E-44.875E-51.S06E-6
5.70E-27.00E-28.50E-21.00E-11.30E-11.6OE-12.20E-12.SOE-13.70E-14.70E-15.70E-17.OOE-1S.SOE-1l.OOE+O1.3OE+O1.60E+02.20E+02.80E+03.70E+04.70E+05.70E+07.00E+0S.50E+01.00E+1i.30E+11.60E+1
1.481E-11.627E-11.77SE-11.9OSE-12.132E-12.318E-12.611E-12.S28E-13.056E-13.215E-13.3O6E-13.355E-13.343E-13.282E-13.0SSE-12.784E-12.164E-11.600E-19.612E-25.199E-22.729E-21.151E-24.171E-31.498E-31.918E-42.461E-5
6.00E-27.50E-29.00E-21.10E-11.40E-1i.SOE-12.40E-13.00E-14.00E-15.00E-16.00E-17.5OE-19-uOE-l1.10E+O1.4OE+O1.80E+02.4OE+O3.00E+04.00E+05.00E+06.00E+07.50E+09.00E+01.1OE+11.40E+11.80E+1
1.516E-11.679E-11.822E-11.987E-12.198E-12.426E-12.691E-12.888E-13.112E-13.248E-13.323E-13.35SE-13.327E-13.222E-12.978E-12.554E-11.966E-11.436E-18.025E-24.295E-22.241E-28.224E-32.967E-37.553E-49.667E-56.286E-6
6. CONCLUSIONS
The results of the present evaluation were used to derive a complete covarianceuncertainty matrix based on integral spectrum data (spectrum averaged cross-sections measurements) and also implicitly taking into account some recent directspectrum measurements (in the prior information). However, these results mustbe updated, and data from direct measurements in particular should be explicitlyincluded in the evaluation as soon as their covariances are available. These datacan easily be combined with the present results. Thus, further steps in theevaluation are necessary in the future in order to obtain an optimum result forthe spectral distribution of 2S2Cf.
PART 1-4 183
REFERENCES
[ 1 ] INTERNATIONAL ATOMIC ENERGY AGENCY, Neutron Cross Sections for ReactorDosimetry (Proc. Consultants Meeting Vienna, 1976), IAEA-TECDOC-208, IAEA,Vienna (1978) 1.
[2] BLINOV, M.V., "Neutron energy spectra of spontaneous fission sources", NeutronSource Properties (Proc. Consultants Meeting Debrecen, Hungary, 1980) (OKAMOTO, K.,Ed.), IAEA/International Nuclear Data Committee, Vienna, Rep. INDC(NDS)-! 14/GT(1980)79.
[3] The Cf-252 Fission Neutron Spectrum (Proc. Consultants Meeting Smolenice, Czechoslovakia,1983) (LEMMEL, H.D., CULLEN, D.E., Eds), IAEA/International Nuclear Data Committee,Vienna, Rep. INDC(NDS)-I46 (1983).
[4] Nuclear Data for Science and Technology (Proc. Int. Conf. Antwerp, 1982) (BO'CKHOFF,K.H., Ed.), Reidel, Dordrecht (1983).
[5] WAGSCHAL, J.J., MAERKER, R.E., BROADHEAD, B.L., ibid., p. 436.[6] BOLDEMAN, J.W., CULLEY, D., CAWLEY, R.W., Trans. Am. Nucl. Soc. 32 (1979) 733.[7] BENSCH, F., JASICEK, H., "The fast neutron emission spectrum of 2S2Cf", Neutron
Source Properties (Proc. Consultants Meeting Debrecen, Hungary, 1980) (OKAMOTO, K.,Ed.), IAEA/International Nuclear Data Committee, Vienna, Rep. INDC(NDS)-114/GT(1980)302.
[8] BLINOV, M.V., VITENKO, V.A., YUREVICH, V.I., in Interaction of Fast Neutrons withNuclei (Proc. Int. Symp. Gaussig, German Democratic Republic, 1979), Zentralinstitutfur Kernforschung, Rossendorf bei Dresden, Rep. ZfK-410 (1980) 104.
[9] MON, Jiangshen, et al., Chin. J. Nucl. Phys. 3(1981) 163.[10] POENITZ, W.P., TAMURA, T., in Nuclear Data for Science and Technology (Proc. Int.
Conf. Antwerp, 1982) (BOCKHOFF, K.H., Ed.), Reidel, Dordrecht (1983) 465.[11] BLINOV, M.V., BOYKOV, G.S., VITENKO, V.A., ibid., p. 479.[12] BOTTGER, R., KLEIN, H., CHALUPKA, A., STROHMAIER, B., ibid., p. 484.[13] MARTEN, H., SEELIGER, D., STOBINSKI, B., ibid., p. 488.[14] BATENKOV, O.I., BLINOV, M.V., BOYKOV, G.S., VITENKO, V.N., RUBCHENYA, V.A.,
"Experimental and theoretical investigation of the energy distribution of californium-5 2spontaneous fission neutrons", The Cf-252 Fission Neutron Spectrum (Proc. ConsultantsMeeting Smolenice, Czechoslovakia, 1983) (LEMMEL, H.D., CULLEN, D.E., Eds),IAEA/International Nuclear Data Committee, Vienna, Rep. INDC(NDS)-146 (1983) 161.
[15] LAJTAI, A., et al., "An absolute measurement of 252Cf prompt fission neutron spectrum atlow energy range", ibid,, p. 177.
[16] MANNHART, W., PEREY, F.G., in Reactor Dosimetry (Proc. 3rd ASTM-EURATOMSymp. Ispra, Italy, 1979) (ROTTGER, H., Ed.), Vol. 2, Commission of the EuropeanCommunities, Brussels, Rep. EUR-6813 (1980) 1016.
[17] MADLAND, D.G., NIX, J.R., in Nuclear Data for Science and Technology (Proc. Int.Conf. Antwerp, 1982) (BO'CKHOFF, K.H., Ed.), Reidel, Dordrecht (1983) 473.
[18] MADLAND, D.G., NIX, J.R., Nucl. Sci. Eng. 81 (1982) 213.[19] MARTEN, H., NEUMANN, D., SEELIGER, D., "Theoretical analysis of the Cf-252
fission neutron spectrum", The Cf-252 Fission Neutron Spectrum (Proc. ConsultantsMeeting Smolenice, Czechoslovakia, 1983) (LEMMEL, H.D., CULLEN, D.E., Eds),IAEA/International Nuclear Data Committee, Vienna, Rep. INDC(NDC)-146 (1983) 199.
[20] PEELLE, R.W., Adv. Nucl. Sci. Technol. 14(1982)11.[21] PEREY, F.G., Oak Ridge National Lab., TN, Rep. ORNL/TM-6062 (1977).[22] PEREY, F.G., Oak Ridge National Lab., TN, Rep. ORNL/TM-6267 (1978).
184 MANNHART
[23] SCHMITTROTH, F., Hanford Engineering Development Lab.. Richland, WA,Rep. HEDL/TME 79-40 (1979).
[24] MANNHART, W., "Approaches for the generation of a covariance matrix for the Cf-252fission neutron spectrum", The Cf-252 Fission-Neutron Spectrum (Proc. ConsultantsMeeting Smolenice, Czechoslovakia, 1983) (LEMMEL, H.D., CULLEN, D.E., Eds),IAEA/International Nuclear Data Committee,Vienna, Rep. INDC(NDS)-146 (1983) 229.
[25] HEATON, H.T., II.GILLIAM, D.M., SPIEGEL, V., EISENHAUER, C, GRUNDL, J.A.,in Fast Neutron Fission Cross Sections of U-233, U-238, Pu-239 (Proc. NEANDC/NEACRP Specialists Meeting Argonne, IL, 1976) (POENITZ, W.P., SMITH, A.B., Eds),Argonne National Lab., IL, Rep. ANL-76-90 (1976) 333.
[26] GRUNDL, J.A., EISENHAUER, C, in Nuclear Cross Sections and Technology (Proc.Int. Conf. Washington, DC, 1975), US National Bureau of Standards Special Publication425, US Government Printing Office, Washington, DC (1975) 250.
[27] MANNHART, W., in Nuclear Data for Science and Technology (Proc. Int. Conf. Antwerp,1982)(B5CKHOFF, K.H., Ed.), Reidel, Dordrecht (1983) 429.
[28] MAERKER, R.E., WAGSCHAL, J.J., BROADHEAD, B.L., Electric Power ResearchInstitute, Palo Alto, CA, Rep. EPRI-NP-2188 (1981).
[29] TAGESEN, S., VONACH, H., STROHMAIER, B., Phys. Data 13-1 (1979).[30] STROHMAIER, B., TAGESEN, S., VONACH, H., Phys. Data 13-2 (1980).[31] TAGESEN, S., VONACH, H., Phys. Data 13-3 (1981).[32] WINKLER, G., SMITH, D.L., MEADOWS, J.W., Nucl. Sci. Eng. 76 (1980) 30.[33] WINKLER, G., PAVLIK, A., VONACH, H., PAULSEN, A., LISKIEN, H., in Nuclear
Data for Science and Technology (Proc. Int. Conf. Antwerp, 1982) (BOCKHOFF, K.H.,Ed.), Reidel, Dordrecht (1983) 400.
[34] PAVLIK, A., WINKLER, G., Evaluation of the s8Ni(n, 2n)S7Ni Cross Sections,IAEA/International Nuclear Data Committee, Vienna, Rep. INDC(AUS)-9/L (1983).
[35] MUIR, D.W., MacFARLANE, R.E., BOICOURT, R. M., in Reactor Dosimetry (Proc.4th ASTM-EURATOM Symp. Gaithersburg, MD, 1982), Vol. 2, US Nuclear RegulatoryCommission, Washington, DC, Rep. NUREG/CP-0029 (1982) 655.
[36] MANNHART, W., "Status and further needs of cross section covariance files", NuclearData for Radiation Damage Assessment and Related Safety Aspects (Proc. AdvisoryGroup Meeting Vienna, 1981), IAEA-TECDOC-263, IAEA, Vienna (1982) 47.
[37] FU, C.Y., HETRICK, D.M., PEREY, F.G., in Nuclear Cross Sections for Technology(Proc. Int. Conf. Knoxville, TN, 1979), US National Bureau of Standards SpecialPublication 594, US Government Printing Office, Washington, DC (1980) 63.
[38] FU, C.Y., HETRICK, D.M., in Reactor Dosimetry (Proc. 4th ASTM-EURATOM Symp.Gaithersburg, MD, 1982), Vol. 2, US Nuclear Regulatory Commission, Washington, DC,Rep. NUREG/CP-0029 (1982) 877.
[39] MANNHART, W., "Information on the Cf-252 fission-neutron spectrum deduced fromintegral experiments", The Cf-252 Fission-Neutron Spectrum (Proc. Consultants MeetingSmolenice, Czechoslovakia, 1983) (LEMMEL, H.D., CULLEN, D.E., Eds), IAEA/International Nuclear Data Committee, Vienna, Rep. INDC(NDS)-146 (1983) 213.
[40] MADLAND, D.G., NIX, J.R., Brookhaven National Lab., Upton, NY, Rep. BNL-51778(1983)423.
[41] MADLAND, D.G., LaBAUVE, R.J., NIX, J.R., "Differential and integral comparisonsof three representations of the prompt neutron spectrum for the spontaneous fission of2s2Cf", Nuclear Standard Reference Data (Proc. IAEA-OECD/NEANDC Advisory GroupMeeting Geel, Belgium, 1984), IAEA-TECDOC-335, IAEA, Vienna (1985) 267.
[42] MARTEN, H., SEELIGER, D., "Measurement and theoretical calculation of the 2s2Cispontaneous-fission neutron spectrum", ibid., p.255.
PART 1-4 185
[43] SEELIGER, D.; personal communication, 1985.[44] BLINOV, M.V., BOYKOV, G.S., VITENKO, V.A., "Experimental study of an energy
distribution shape of spontaneous fission neutrons of californium-252", NeutronPhysics (Proc. 6th All-Union Conf. Kiev, 1983), IAEA/International Nuclear DataCommittee, Vienna, Rep. INDC(CCP)-238/L (1984).
[45] MARTEN, H-, RICHTER, D., SEELIGER, D., "Analysis of experimental data on thehigh-energy end of the 252Cf spontaneous-fission neutron spectrum", IAEA/InternationalNuclear Data Committee, Vienna, Rep. INDC(GDR)-28L (1984).
1-5. DECAY DATA FOR RADIONUCLIDESUSED AS CALIBRATION STANDARDS
A. LORENZNuclear Data Section,Division of Research and Laboratories,International Atomic Energy Agency,Vienna
Abstract
DECAY DATA FOR RADIONUCLIDES USED AS CALIBRATION STANDARDS.A tabulation of the most current evaluated values of gamma ray energies and emission
probabilities, used as calibration standards in nuclear data measurements, is given.
1. INTRODUCTION
The most current evaluated values of gamma ray energies and emission proba-bilities of radionuclides used as calibration standards in nuclear data measurementsare presented in Table I. The tabulated data have been selected from the mostrecent available evaluations on the basis of their use by individual groups performingdecay data measurements. This compilation was reviewed by members of the IAEA/International Nuclear Data Committee (INDC) Standards Subcommittee and theIAEA Co-ordinated Research Programme for the Measurement and Evaluation ofTransactinium Isotope Nuclear Decay Data. It is also derived from the 1982 editionof the INDC-OECD/Nuclear Energy Agency Nuclear Data Committee (NEANDC)Nuclear Standards File, published as an IAEA technical report [ 1 ]. The reader isreferred to the first chapter of this Handbook for the corresponding half-lives.
2. SELECTION OF STANDARDS INCLUDED IN THE FILE
The radionuclides chosen to be included in this review were selected on thebasis of their inclusion in the following compilations:
(1) The INDC/NEANDC Nuclear Standards File [2].(2) The list of standards for gamma ray energy calibration recommended by the
International Union of Pure and Applied Physics (IUPAP,) [3].
187
188 LORENZ
(3) The report by the Atomic Energy of Canada Ltd (AECL) Radio isotopeStandardization Group to the Spectrometry Working Group of the Inter-national Committee for Radionuclide Metrology (ICRM) [4].
(4) The list of radionuclides used as standards by groups performing transacti-nium isotope decay measurements.
3. SELECTION OF RECOMMENDED GAMMA RAY ENERGIES ANDINTENSITIES
Following the recommendation of the INDC Standards Subcommittee, allgamma ray energy standards recommended by the IUPAP Commission on AtomicMasses and Fundamental Constants [3] were adopted for those radionuclidesincluded in this file. Beyond this initial criterion, the recommended values of Eand P were selected from the following sources of evaluated data:
(1) Emission probabilities of selected gamma rays for radionuclides used asdetector calibration standards [5].
(2) Evaluations of gamma ray energies and emission probabilities performedspecifically for Ge(Li) spectrometer calibration (see Refs [6-9]).
(3) The Laboratoire de metrologie des rayonnements ionisants (LMRI) tablesof radionuclides [10-15].
(4) The evaluation of gamma ray intensities [16].(5) Nuclear spectroscopy standards listed in the publication Table of Isotopes [17].(6) The report of the AECL Radioisotope Standardization Group [4].(7) The journal Nuclear Data Sheets.(8) The Table of Isotopes (used primarily in those cases where the isotope has
not been evaluated since 1976 [17].
4. KEY TO THE COMMENTS COLUMN IN THE TABLE
The numbers and letters in the comments column should be read individually.
1 — Gamma ray lines of radionuclides included in the list of standards for gammaray energy calibration recommended by the IUPAP [3].
2 - Radionuclides used as standards by groups performing transactinium isotopedecay measurements.
3 - Radionuclides included in the list of gamma ray standards submitted to thea-, j3- and 7-ray Spectrometry Working Group of the ICRM [4].
4 - Radionuclides included as gamma ray standards in the 1982 INDC/NEANDCNuclear Standards File [1 ].
P - Radionuclides considered in Ref. [5] as primary references.5 - Radionuclides considered in Ref. [5] as secondary references.
Text cont. on p. 195.
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PART 1-S 195
REFERENCES
[ 1 ] INTERNATIONAL ATOMIC ENERGY AGENCY, Nuclear Data Standards for NuclearMeasurements, Technical Reports Series No. 227, IAEA, Vienna (1983).
[2] INDC/NEANDC Nuclear Standards File, 1978, IAEA/International Nuclear Data Committee,Vienna, Rep. INDC-30/L+Sp (1980).
[3] HELMER, R.G., VAN ASSHE, P.H.M., VAN DER LEUN, C, Recommended standards forgamma-ray energy calibration, At. Data Nucl. Data Tables 24 (1979) 39-48.
[4] RUTLEDGE, A.R., SMITH, L.V., MERRITT, J.S., Decay Data for Radionuclides Usedfor the Calibration of X- and 7- Ray Spectrometers, Atomic Energy of Canada Ltd,Chalk River Nuclear Labs, Chalk River, Ontario, Rep. AECL-6692 (1980).
[5] VANINBROUKX, R., "Emission probabilities of selected gamma rays for radionuclidesused as detector-calibration standards", Nuclear Standard Reference Data (Proc. IAEA -OECD/NEANDC Advisory Group Meeting Geel, Belgium, 1984), IAEA-TECDOC-335,IAEA, Vienna (1985) 403-412.
[6] HELMER, R.G., GREENWOOD, R.C., GEHRKE, R.J., Nucl. Instrum. Methods 155(1978) 189.
[7] GREENWOOD, R.C., HELMER, R.G., GEHRKE, R.J., Nucl. Instrum. Methods 159(1979)465.
[8] HELMER, R.G., CAFFREY, A.J., GEHRKE, R.J., GREENWOOD, R.C., Nucl. Instrum.Methods 188(1981) 671.
[9] SCHOETZ1G, U., DEBERTIN, K., WALZ, K.F., Nucl. Instrum. Methods 169 (1980) 43.[ 10] Table of Radionuclides (LAGOUTINE, F., Evaluator), CEA Centre d'etudes nucleates
de Saclay, Laboratoire de metrologie des rayonnements ionisants, Gif-sur-Yvette (1979).[11] Table of Radionuclides (LAGOUTINE, F., Evaluator), CEA Centre d'etudes nucleates
de Saclay, Laboratoire de metrologie des rayonnements ionisants, Gif-sur-Yvette (1977).[12] Table of Radionuclides (COURSOL, N., LAGOUSTINE, F., Evaluators), CEA Centre
d'etudes nucleaires de Saclay, Laboratoire de metrologie des rayonnements ionisants,Gif-sur-Yvette (1980).
[13] COURSOL, N., Private communication, CEA Centre d'etudes nucleaires de Saclay,Laboratoire de metrologie des rayonnements ionisants, Gif-sur-Yvette, 1981.
[14] COURSOL, N., Private communication, CEA Centre d'etudes nucleaires de Saclay,Laboratoire de metrologie des rayonnements ionisants, Gif-sur-Yvette, 1982.
[15] COURSOL, N., Private communication, CEA Centre d'etudes nucleaires de Saclay,Laboratoire de metrologie des rayonnements ionisants, Gif-sur-Yvette, 1984.
[16] YOSHIZAWA, Y., et a]., Evaluation of Gamma-ray Intensities, Japan Atomic EnergyResearch Institute, Tokyo, Rep. JAERI-M-8811 (1980).
[17] Table of Isotopes, 7th edn (LEDERER, CM., SHIRLEY, V.S., Eds), Wiley, New York(1978).
[18] AUBLE, R.L., Mass chain evaluation A=56, Nucl. Data Sheets 20 3 (1977) 253.[19] ANDERSSON, P., EKSTROEM, L.P., LYTTKENS, J., Mass chain evaluation A=59,
Nucl. Data Sheets 39 4 (1983) 641.[20] HALBERT, M.L., Mass chain evaluation A=64, Nucl. Data Sheets 28 2 (1979) 179.[21] HARMATZ, B., Mass chain evaluation A=l 11, Nucl. Data Sheets 27 3 (1979)453.[22] LYTTKENS, J., et al., Mass chain evaluation A=l 13, Nucl. Data Sheets 33 1 (1981) 1.[23] TAMURA, T., MIYANO, K., OHAYA, H., Mass chain evaluation A=124, Nucl. Data
Sheets 41 (1984) 413.[24] Handbook of Radioactivity Measurement Procedures (MARTIN, M.J., Ed.), National
Council on Radiation Protection and Measurements, Washington, DC, Rep. 58 (1978),Appendix.
196 LORENZ
[25] LEE, M.A., Mass chain evaluation A=153, Nucl. Data Sheets 37 (1982) 487.[26] SHIRLEY, V., Mass chain evaluation A=169, Nucl. Data Sheets 36 4 (1982) 443.[27] SCHMORAK, M.R., Mass chain evaluation A=170, Nucl. Data Sheets 15 3 (1975) 371.
Part 2
NEUTRON ACTIVATION
2-1. THERMAL NEUTRON CROSS-SECTIONSAND INFINITE DILUTIONRESONANCE INTEGRALS
E. GRYNTAKIS, D.E. CULLEN, G. MUNDYNuclear Data Section,Division of Research and Laboratories,International Atomic Energy Agency,Vienna
Abstract
THERMAL NEUTRON CROSS-SECTIONS AND INFINITE DILUTION RESONANCEINTEGRALS.
The compilation comprises recommended values for thermal neutron cross-sections andresonance integrals (including the 1/v contribution) of nuclides (hydrogen to fermium) forneutron capture and fission reactions. The main gamma rays of neutron capture, their absoluteintensities and, for the non-1 /v nuclide, the g(T = 20°C) Westcott factors are also given.
1. INTRODUCTION
The table of resonance integrals presented in this chapter is based on the com-pilations of Gryntakis and Kim [ 1 ], which include all experimental, calculated and recom-mended values of resonance integrals available in the literature up to August 1981.Using the resonance integrals from this compilation, together with some newresults (published up to January 1985), the recommended values of resonance integralsfor nuclides from hydrogen to fermium have been evaluated here. The givenvalues are in most cases the mean values of the existing experimental results, whilethe given error is the standard deviation of these results. In some cases, becauseof the large disagreement between the few existing results, the recommendedvalue was selected based on a single measurement. Whenever possible the isotopicthermal neutron cross-sections and resonance integrals were renormalized in orderto be in agreement with the corresponding values of the natural element. For mostof the thermal cross-sections, the recommended values are those given in Ref. [6].Most of the values of the g(Tn = 20°C) Westcott factors are taken from Ref. [307],in which the g(Tn) functions for about 50 (n/y) and (n,f) reactions of non-1/vnuclides were calculated for the temperature range 0 to 2000°C.
Some radioanalytical laboratories have recently introduced in activationanalysis the concept of the effective resonance energy, first proposed by Ryves(see Ref. [ 1 ] in the Annex) for the correction of the epithermal flux to an ideal
199
200 GRYNTAKIS et al.
1/E flux. A paper by F. De Corte, giving explanations on the calculations of theeffective resonance energies, is included here as an annex.
All of the resonance integrals given in Table II are from the cadmium cut-offenergy (Ec = 0.5 eV) to infinity and include the 1/v contribution. The usershould not confuse these with the excess resonance integrals (the 1/v contributionsexcluded) or with the resonance integrals from /nkT energy. The theoretical andphysical meanings of the different resonance integrals, and the methods for theirdetermination, are explained in Ref. [ 1 ] and for convenience have been reproducedbelow.
2. DEFINITION OF A RESONANCE INTEGRAL
The microscopic cross-section averaged over a pure 1/E flux is the resonanceintegral:
1= / a(E)dE/E (for the 1/E spectrum) (1)
where El and E2 are the lower and the upper limits of the 1/E flux, respectively.When the a(E) function for a specific nuclide reaction is known, the
resonance integral can be easily calculated using Eq. (1). Theoretically, theCT(E) function can be determined from the following Breit-Wigner formula [413],or by similar formulas:
(2)
where X is the de Broglie wavelength, g is a statistical factor, Er is the resonanceenergy and Fn , F and F are the neutron, radiative and total widths, respectively.
In the usual manner of determining the resonance integral experimentally,the target nuclide is irradiated in a reactor spectrum which can be assumed tobe the sum of two components, a Maxwellian distribution corresponding to T(°K)and a 1/E epithermal flux with lower limit jukT, where k is the Boltzmannconstant and n varies with the type of reactor. For D2O reactors, ji is about 5and for some graphite reactors about 3, so that at T = 293.6°K, /ikT will in thesecases be equal to about 0.126 and 0.076 eV, respectively. The two spectra arecontinuous and overlap each other at a neutron energy of about 0.5 eV. Whena nuclide is irradiated in this spectrum, the activation result of the resonanceintegral must be corrected by subtracting the contribution of the Maxwelliancomponent and thus the expression becomes
PART 2-1 201
OO
I', = J [a(E)-g(T)aoV/E^E]dE/E (3)
//kT
where g(T) is a parameter depending on the neutron temperature (see Section 3)and Eo = 0.0253 eV.
The usual experimental method of separating the thermal cross-section dueto the Maxwellian spectrum and the resonance integral due to the 1/E spectrumis to irradiate a nuclide under a Cd filter which absorbs neutrons below theeffective Cd cut-off energy (Ec). Calculations of this cut-off energy for variousshapes and thicknesses of the Cd filter have been made by several authors [207,292, 379]. In these calculations, it is observed that a small cylindrical Cd filterof 1 mm thickness has a cut-off energy of about 0.55 eV. Under this condition,the resonance integral is divided into two parts: one between //kT and Ec andthe other from Ec to «>, so that Eq. (3) becomes
Ec
I'i = A [a (E) -g (T)a o v / E^E]dE/E
+ J [o(E) - g(T)a0
E c
= [AI-AI(l/v)] + [ I - I(l/v)] = AI' + I' (4)
where I' is the epicadmium resonance integral (excluding the 1/v part) and AI'is the part (shielded by a Cd filter) which depends on the neutron temperatureand is negligibly small for nuclides obeying the 1 /v law in the thermal energyregion. However, for those nuclides where a resonance peak lies near the cut-offenergy, such as u3Cd, 151Eu, 176Lu, 182Ta, m I r , 231Pa, 239Pu, etc., the value ofAI' becomes very large and cannot be neglected. When the resonance peak appearsnear the cut-off energy (Er = Ec), AI' can be calculated from the expression [368]:
AI'/I' = {r/irET)[(2/^TT) (VE7 - V T O
V E 7 T ; (5)
where T and Er are the resonance width and the resonance energy, respectively.Since AI' is a temperature-dependent term, its evaluation must follow thetemperature of the neutron spectrum.
202 GRYNTAKIS et al.
TABLE I. RESONANCE INTEGRALS
Symbol Meaning Limits Remarks
I
Kl/v)
I
I'l
Al'
Epicadmium excessresonance integral
1/v part of resonanceintegral
Epicadmium resonanceintegral including the1/v part
Excess resonanceintegral
Excess resonance integralbelow E energy
Ecto°°
Ec to°°
E c to°°
[jkT to °°
to E
Cd filter method: Eq. (4)
Eq. (6)
I = I' + I (1/v)
Method withoutCd filter (Eq. (4))
Al' = I1, - 1 '
The data from available literature on the epicadmium resonance integralrepresent either the value of I' or I, which then includes the 1/v part [I(l/v)].This 1/v tailing can be easily calculated if the cut-off energy is known:
I(l/v) = I - I' = J g(T)a0
Ec
dE/E = 2g(T)a0 (6)
The meanings of the several resonance integrals are summarized in Table I.
3. EXPERIMENTAL MEASUREMENT WITH A Cd FILTER
3.1. The Westcott method
According to Westcott (Ref. [292]), the reaction rate per target atom isgiven by
R = = nv0 a0 [g(T) + r (7)
where
= nv0 is the neutron flux defined as the total neutron density times the2200 m/s velocity;
PART 2-1 203
a(T) is the effective cross-section:a0 is the thermal cross-section for 2200 m/s neutrons;g(T) is the parameter which represents the departure of the cross-section
from the 1 /v law in the thermal region (g(T) = 1 if the nuclideobeys the 1/v law in this energy region) and which can be calculatedfrom the expression:
= ( l / f f 0v 0)J [(4/Vir)(v3/v|)exp(-v2/v|)]ff(v)dv (8)
0
or
g(T) = _ 2 _ / y/E a(E) sfEWj exp(-E/ET) dE/ET (8a)\/iTy/Eoao J
0
where ET = E0T/T0, Eo = 0.0253 eV and To = 293.6°K.The g(T) functions foT about 50 non-1 /v reactions of the (n,7), (n,f) and
(n, abs) types have been calculated in the temperature range from 0 to 2000°Cin Ref. [307]. The r-\/T/T0 is the epithermal index which denotes the strengthof the epithermal flux. It is zero for a pure thermal flux and can be determinedwith the knowledge of the Cd ratio (CR) of a monitor nuclide:
r V T C = g(T)/[(CR-l)s0 + 4g(T)CRVEo/7rEc] (9)
s0 is the parameter which represents the ratio of the resonance integral andthermal cross-section such that
/V 7 r a o(10)
The epicadmium resonance integral (I') can be determined by measuringthe CR of the nuclide of interest at the irradiation position, where the epithermalindex is already known:
(11)
The epithermal index can be determined either using Eq. (9) or from theirradiation without Cd cover of two different monitor nuclides, one sensitiveto thermal activation and the other sensitive to epithermal activation [179, 382]:
204 GRYNTAKIS et al.
= [g,(T)CT01 -g2(T)ao2Ri /2]/(so2CT02R1/2-s01a0i) (12)
where R^2 = 6i/62, which may easily be determined by the activity ratio of
monitors 1 and 2.
3.2. The common method
This method, theoretically less rigorous, but commonly used (see Refs [207]and [146]),defines the reaction rate by
where
CTjjj, I are the subcadmium and epicadmium cross-sections, respectively;4>^ is the neutron flux defined as the thermal neutron density times the
2200 m/s neutron velocity;0 • is the epithermal flux per unit ln(E).
From the knowledge of the Cd ratio of a monitor nuclide the ratio of theepicadmium flux can be determined as
or
0m KCR-1)
From Eqs (7) and (13) it follows that
OQ. = g(T)a0 + — ( 1 -2VE0-E c)g(T)a0 (15)
4
o t h=g(T)ao+-S E[AI (-I(l/v)] (15a)
The quantity [AI' —I(l/v)] results in a positive or negative value dependingon whether a nuclide follows the 1/v law or not. When the activation is performedin a reactor neutron spectrum with low epithermal flux (0epj - 0^), a^ =g(T)a0.The epicadmium resonance integral, including the 1/v tailing, can then be deter-mined with the knowledge of the Cd ratios for the nuclide of interest (x) and themonitor (s):
l)xa ths] (16)
PART 2-1 205
Many authors often assume that a^ = a0 in order to calculate the epicadmiumresonance integral (I). However, such an assumption is not completely justified,unless the nuclide obeys the 1/v law and the activation is undertaken in a wellthermalized neutron spectrum (0 • < 4>^l)- For obvious reasons, it is clear thatthe epicadmium resonance integral thus determined should not be consideredas a constant physical parameter [379]. The quantity of the 1/v tailing includedin the epicadmium resonance integral varies with respect to the Cd cut-off energy(Ec), which is a function of the thickness of Cd, its shape, neutron energy andangle of incidence and also of the neutron temperature (see Eq. (6)).
4. EXPERIMENTAL MEASUREMENT WITHOUT A Cd FILTER
When the evaluation of the resonance integral is very sensitive to the Cdcut-off energy (Ec) due to the presence of low energy resonances which contributesignificantly to the total resonance integral, the use of a Cd filter does not lead toan appropriate differentiation of the thermal cross-section and resonance integral.On the contrary, the measured value of the resonance integral is sharply reducedby the absorption of neutrons near the Cd cut-off energy. The solution to thisproblem relies on the special method which differentiates the neutron spectrumwithout the use of a Cd filter, but with knowledge of the relationship betweenthe two different neutron spectra [179].
Looking at Eq. (7), one notices that the effective cross-section varies as afunction of g(T) and epithermal index (r-y/T/To), which are temperature-dependent quantities. When irradiation is performed in two different neutronspectra having different neutron temperatures and epithermal components, theconstant value s0 can be determined from the knowledge of the ratio betweeneffective cross-sections, provided that g(T) and the epithermal indices are knownfor the two spectra:
s0 =(2v^r)(I'1/a0)= [R1/2g2(T)-g1(T)]/[(rVt7T7)i-Ri/2(rN/T7T7)2](17)
where R ^ is equal to Oi/Sj from two different irradiation positions.With Eq. (17) it is possible to determine directly the Ii value, which other-
wise can only be evaluated through tedious and approximate corrections forneutron attenuation, absorption and perturbation by the Cd filter used.
Explanation of the columnsin Table II is given on p. 248.
TABLE II. RECOMMENDED VALUES FOR THERMAL NEUTRON CROSS-SECTIONS AND RESONANCE
INTEGRALS OF NUCLIDES FOR NEUTRON CAPTURE AND FISSION REACTIONS o\
TARGET NUC
Z-SYMBOL-A
1-H -NAT
1
2
3
2-HE-NAT
3
4
3-LI-NAT
6
7
4-BE- 7
9
10
5-B -NAT
10
1 1
6-C -NAT
LIDE
ABUNDANCE IX)]OR HALF-L IFE 1
-
99.985
0.015
•12.346Y
-
1.3E-4
99.99987
-
7 . 5
92.5
•53.40D
100
•1 .6E+6Y
-
2 0
8 0
-
A+1 NUCLIOE
HALF-LIFE
-
-
12.346Y
-
-
-
-
84 4 MS
1.6E+6Y
13.8S
-
-
0.0203S
-
1S0MERSTATEIT l%l
-
-
-
-
-
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ABS
ACT
N.P
ACT
ACT
AE3S
ACT
N.A
ACT
N . P
N.A
ACT
ACT
ACT
ADS
ACT
ABS
ACT
ACT
THERMALC R O S S - S E C T I O N S
Ib)AND
j ( T ) FACTOR
0.3326+-0.0007
0.3326+-0.0007
<0.5l9*-0.007)E-3
<0.006E-3
(0.040»-0.010)E-9
0.0069*-0.0001
(0.031t-0.009)E-3
533S+-7
0.0
0.0448+-0.0030
70.5t-0.3
0.0385*-0.0030
940+-4
0.0454<-0.0030
48000*-9000
<0. 1
0.0076+-0.0008
<0.001
0.10t-0.09
7674-4
0.5+-0.2
38374-9
0.00554-0.0033
(3.50*-0.07>E-3
RESONANCEINTEGRALS
(bl
0 .1489
0.1489
6.298E-4
0.00314-0.0001
2401 4- 1 0
32
425.5
0.01756
21940
0.O04O+-0.0004
344.4^-2.2
1722+-10
0.0757
(1,55*-0.05)E-3
RESONANCEINTEGRALS:REFERENCES
4 09
4 09
6 409
11
4 09
4 09
4 09
6 409
6 13
6 409
4 09
MAIN GAMMA RAYS FOR A* 1NUCLIOE
ENERGY (keV)(ABSOLUTE INTENSITY: X )
o
2
n
E.
4439( 3 )
TARGET NUC
Z-SYMBOL-A
12
13
14
7-N -NAT
14
15
8 -0 -NAT
16
17
18
L10E
ABUNDANCE 1X1OR H A L F -LIFE
98.89
1.11
•5730Y
-
99.64
0.36
-
99.756
0.039
0.205
A* l NUCLIOE
HALF-L.FE
-
5736Y
2.46S
-
-
7. 14S
-
-
27 . IS
ISOMERSTATEIT IX)
-
-
TYPEOF
REACT1ON
ACT
ACT
ACT
ACT
ABS
ACT
N . P
ACT
ACT
ACT
ACT
N.A
ACT
THERMALCROSS-SECTIONS
IblAND
g(T) FACTOR
( 3 . 5 3 + - 0 . 0 7 I E - 3
( 1 . 3 7 » - 0 . 0 4 ) E - 3
<0.001E-3
0.0747»-0.0073
1.90>-O.O3
0.0750*-0.0075
1.83+-0.03
(O.024 + -O. 008)E-3
( 0. 19»-0.02JE-3
(0 . 190+-0.019)E-3
(0.538 + -0.0651E-3
O.235+-0.010
(0.16 + - 0 . 0 1 ) E - 3
RESONANCEINTEGRALS
Ibl
( 1 . 5 7 - 1 - 0 . 0 5 ) 6 - 3
0 . 0 0 1 7 + - 0 . 0 0 0 2
0.034
4 . 8 + - 2 . 4
0.034
0.00011
0.00036
,0.00036
0.00039
( 0 . 8 7 + - 0 . 0 4 ) E - 3
RESONANCEINTEGRALS:REFERENCES
6 409
6
6
6 13
6
6
6 409
6
6 311
MAIN GAMMA RAVS FOR A * lNUCLIDE
ENERGY IkeVI(ABSOLUTE 1NTENSITY:%)
5298( 6 8 )
6129 7117( 6 9 ) ( 5 )
110 197 1356 1444 1550( 3 ) ( 9 0 ) ( 5 0 ) ( 3 ) ( 2 )
7>
9-F - 19
10-NE-NAT
20
21
2 2
11-NA- 22
23
100
-
90.5
0.27
9.23
•2.60Y
100
11.OS |
-
-
-
3 8 5
-
O.02S
15.03H
-
M1TM00
G
M»G
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
O.0096+-0.0005
0.039+-0.007
0.037+-0.004
O.666+-O.110
0.0455*-0.0060
29000+-1000
0.40+-0.03
0. 13*-0.03
O.530*-O.OO7
0
0
0
0
0
(
0
.039»-0.003
.0188
.0175
.296
.023
170*-30)E»3
,320*-0,015
6
6
6
6
6
6144399
13
3 1 6
101524 09
3 1 2
396
11154
4 0 9
23 47 124 128312 314 315 398
1634( 100)
440(33)
1369 2754( 100M 100)
12-MG-NAT ACT 0.063<-0.005 |0.O38*-O.0O<! 11 14 <>] 4 0 9
O
TABLE II
TARGET NUC
(cont.)
L1DE
Z-SVMBOL-A ABUNDANCE!*)OR HALF-ILIFE
24
25
26
27
13-AL- 27
14-SI-NAT
28
29
30
31
15-P - 31
16-S -NAT
32
33
34
36
17-CL-NAT
78.99
10. 00
11.01
•9.46M
100
-
92.2
4.7
3. 1
•2.62H
100
-
95.0
0.75
4.2
0.015
-
A*1 NUCLIDE
HALF-LIFE
-
-
9.46M
21 . HI
2.246M
-
-
2.62H
280Y
14.30
-
-
-
-
5. 1M
-
1SOMERSTATEIT 1%)
TVPEOF
REACTION
ACT
ACT
ACT
ACT
|ACT
-
-
-
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ABS
N.A
N.P
ACT
N.A
ACT
N.A
N.P
ACT
ACT
ACT
ABS
THERMALCROSS-SECTIONS
Ib)AND
,(T) FACTOR
0.051+-0.005
0.190+-0.030
0.035+-0.002
0.07+-0.02
0.232t-0.003
0. 171+-0.006
0.177t-O.O0G
0. 10U-0.014
0.107*-0.002
0.18+-0.04
0.172*-0.006
0.52+-0.01
0.53+-0.01
0.008+-0.004
<0.015+-0.008)E-3
0.53+-0.04
0.007*-0.004
0.35+-0.04
0. 190*-0.080
0.002+-0.001
0.240+-0.010
0.15+-0.03
33.1+-0.3
33.5+-0.3
RESONANCEINTEGRALS
Ib)
0.032-1-0.004
0.098+-0.015
0.027+-0.002
0. 175 + -0.005
0. 127+-0.018
0. 110*-0.015
0.077+-0.015
0.66+-0.060
0.085+-0.010
0. 10
0.08
0.097
0.534*-0.023
0. 17+-0.04
14.0+-1.0
6
6
6
6312
11
6
6
6
6
1 1
6
6
6
6
6
23
10339
409
312
10
4 09
394
317
1 1
RESONANCEINTEGRALS:REFERENCES
312 339 398 399 432
11 14 22 23 41398 399 4 09
432
1 1 409 432
13 318 409
MAIN GAMMA RAVS FOR A* 1NUCLIDE
ENERGV (keV)(ABSOLUTE INTENS!TV:%)
844 1014(72) (28)31 401 941 1342 1373
(66) (37) (38) (53) (5)
1779( 100)
3102(90)
208G
RY
NT
v>re
TARGET NU(
Z-SYMBOL-A
3 5
3 6
37
18-AR-NAT
3 6
37
3 8
3 9
4 0
4 1
19-K -NAT
3 9
4 0
4 1
LIDE 1 A*1 NUCLIOE
ABUNDANCE IMI HALF-OR HALF- L IFELIFE |
75.77
•3.0F.45Y
24.23
-
0.34
•34.8D
0.07
'269V
99.59
• 1.83H
-
93.3
0.012•1.3E+9Y
6.70
3.0E45Y
-
IS
37.18M
-
34.80
-
-
269Y
-
1 .83H
33V
-
12.36H
1S0MERSTATEIT (XI
MI T - 1 0 0
G
M«G
-
-
1.3E+9Y
TVPEOF
REACTION
N . P
ACT
N . P
N.A
ACT
ACT
ACT
ACT
ACT
ACT
N.A
N.A
N . P
ACT
ACT
ACT
ACT
ACT
ACT
N.A
ACT
N.P
N.A
ACT
THERMALCROSS-SECTIONS
IblAND
, ( T ) FACTOR
0.37t-O.02
43.64-0.4
0.4894-0.014
(0.084-0.04)E-3
< 1 0
0.0474-0.010
0.3764-0.011
0.4234-0.007
0.675*-0.009
5.24-0.5
0.00554-0.0005
19704-330
694-14
0 .8 *0 .2
6004-300
0.6604-0.010
0.5»-0.1
2. 14-0. 1
2. 14-0.2
0. 00434-0. 0005
304-8
4.44-0.3
0.394-0.03
1.464-0.03
RESONANCEINTEGRALS
Ibl
184-2
0.304-0 .06
0.434-0.03
2 . 5 4 - 0 . 5
0 .44 -0 .1
0.424-0.03
1 . U - 0 . 1
1 . 14-0.1
134-4
2 .04 -0 .2
1 .404-0 . 10
RESONANCEINTEGRALS:REFERENCES
6 317
6 21 23 312 399
6 4 09
6
6
6 319
6
6
6
6
6 23 58 65 312 320 399432
MAIN GAMMA RAYS FOR A*1NUCLIDE
ENERGY IkeVI(ABSOLUTE INTENSITY: X )
1642 2168( 3 2 ) ( 4 4 )
1294(99)
1461(100)
1525( 18)
"0
JO
20-CA-NAT |ACT 1 0 . 4 3 4 - 0 0 2 0 . 2 3 4 - 0 . 0 2
toO
TABLE II (cont.) too
TARGET NUC
Z-SYMBOL-A
4 0
4 1
4 2
43
44
45
46
48
21-SC- 45
4 6
22-TI -NAT
4 6
47
4 8
4 9
5 0
23-V -NAT
5 0
51
LIDE
ABUNDANCEIXIOR H A L F -LIFE
96.94
•1 .3E+5Y
0.65
0. 14
2.08
»165D
0.003
0. 19
100
•84.00
-
8 . 0
7 . 5
73.7
5.54
5 . 3
-
0.25
99.75
A«l NUCLIDE
HALF-LIFE
1.3E»5Y
-
-
-
165D
-
4.54D
8.72M
18.7S
84. 0D
3.420
-
-
-
-
-
5.8M
-
-
3.75M
ISOMERSTATEIT IXI
MIT=100
G
M*G
-
-
TYPEOF
REACTION
ACT
N . A
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
1b)AND
g ( T ) FACTOR
0 . 4 1 + - 0 . 0 2
O.0025*-0.0011
4
0.680+-0.070
6.2+-0.6
0.88+-0.05
15
0.74+-0.07
1.09*-0.14
9.8+-1.1
17.4 + - 1 . 1
27.2+-0.2
8.0+-1.0
6.09+-0.13
0.59+-0.18
1.7+-0.2
7.84+-0.25
2.2+-0.3
0. 179*-0.003
5.07+-0.11
60+-40
4.93+-0.06
RESONANCEINTEGRALS
Ib)
0 . 2 2 * - 0 . 0 2
0.39+-0.04
3.93 + - 0 . 15
0.56+-0.01
0.32*-0 .12
0.90»-0.10
5 . 4 t - 0 . 6
6 .1+-0 .8
11 .5* -0 .5
3 .1+-0 .2
0.30*-0 .09
1.5+-0.2
3 . 9 * - 0 . 2
1.2+-0.2
0.120*-0.015
2 .7+-0 .1
43+-15
2 . 6 * - 0 . 1
6
6
6
6
6
6
6
2312
6
6
6
6
6
2
6
6
3234 05
102
47
312
6399
1 1
6
13
63244 09
RESONANCEINTEGRALS:REFERENCES
4 3 2
10 11 47
13 109
23 312 398
14
10 11 23334 365 398
48 154
3 9 9
312 320399 4 03
MAIN GAMMA RAYS FOR A«1NUCLIDE
ENERGY IkcVI(ABSOLUTE INTENSITY: %)
489( 7 )
3084(92)
889( 100)
159(68)
320(93)
1434( 100)
808(7)
4072(7)
1121100)
609(1)
1297(75)
929(7)
o50•ZH
5>
24-CR-NAT I ACT | 3 . 0 7 t - 0 . ( 6 11 13 324 325 409
TARGET NU
Z-SYM80L-A
50
52
53
54
25-MH- 53
54
55
26-FE-NAT
54
56
57
58
27-CO- 58M
G
59
60M
G
28-N1-NAT
LIDE
ABUNDANCE HIOR HALF-L1FE
4.35
83.79
9.50
2.36
•3.7E»6Y
•312.5D
too
-
5.8
91.7
2. 19
0.31
•8.94H
•70.780
100
• 10.5M
•5.272Y
-
A«1 NUCLIDE
HALF- 1ISOMERLIFE STATS
1 IT IX)
27. 7D
-
-
3. COM
312.5D
-
2.58H
-
2.7Y
-
-
44.60
-
-
10. SM
5.272Y
99. OM
-
-
MIT-99.7
G
M + G
-
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
IblANO
,(T) FACTOR
15.9»-0.2
0.76+-0.06
18.2+-1.5
O.36+-0.04
70t-10
38
I3.3»-O.2
2.56*-0.03
2.25+-0. 18
2.59+-0. 14
2.48+-0.30
1 .28*-0.05
1400OO*-1O0OO
1880+-I2O
18.80+-1.50
18.65+-1.70
37.45+-0.45
58.*-8
2.0»-0.2
4.49*-0. 16
RESONANCEINTEGRALS
Ib)
8. l-t-0.5
0.33t-0.04
9.5+-1.0
0.08+-0.03
30.5*-5.0
17
13.8+-0.4
1.4«-0.2
1.2+-0.2
1.4+-0.2
1.6*-0.2
1.4 + -0.1
540000+-200000
6890
39.7*-4.3
31.4+-4.8
71 .1+-1.8
230*-50
4. 1 •-1.0
2.8+-0.3
2398
6
6
6
6
6
241
266327
64 09
6
6
6
2312
275
G
339
339
21253284 03
6
6
61 17
6399
324
324
324
645
309328
1 1
6398
34 1
9
6129329409
344
344
1 14 09
RESONANCEINTEGRALS:REFERENCES
46
325
325
325
1060312329
13
47
342
1 1146337
444
13
58
11122314330
14
48
13154338
14
312
13125320331
41
58
45166339
17
324
14128322332
45
154
47312340
41
325
22152326333
336
156
96314377
45
MAIN GAMMA RAYS FOR A* 1NUCLIDE
ENERGY IkeV)(ABSOLUTE INTENSITY:*)
320( 10)
835
847(99)
192(3)
181 1(27)
1099(56)
826 1333(3)(100)1173 1333
( 100M 100)
67(86)
909(3)
21 13(14)
1292(44)
"0s
TABLE II (cont.) toto
TARGET NUC LIDE
Z-SYMBOL-A ABUNDANCE IX)OR HALF-
ILIFE
5 8
59
6 0
61
6 2
6 3
64
65
29-CU-N/lT
6 3
6 5
6 6
30-ZN-NAT
6 4
6 5
6 6
67
6 8
6 7 . 7 6
'7 .5E+4Y
2 6 . 4 2
1 . 16
3 . 7 1
M00Y
0.95
•2.52H
-
69.1
30.9
'5.10M
-
48.9
•265D
27.8
4. 1
18.6
Atl NUCLIDE
HALF-LIFE
7.5E*4Y
-
-
-
100Y
-
2.52H
54 . 6H
-
12.7H
5. 10M
61 . 9H
-
2650
-
-
-
1 3 . 9 1 1
ISOMERSTATEIT IX]
-
-
MIT-99
TYPEOF
REACTION
ACT
N.A
ACT
ABS
N . P
N.A
ACT
ACT
N.A
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
N.A
ACT
N.A
ACT
ACT
THERMALCROSS-SECTIONS
Ib)AND
g ( T ) FACTOR
4 . 6 + - 0 . 3
< 0 . 0 0 0 0 3
7 7 . 7 + - 4 . 1
9 2 + - 4
2 . 0 + - 0 . 5
1 2 . 3 + - 0 . 6
2 . 9 + - 0 . 2
2 . 5 + - 0 . 8
< 0 . 0 0 0 0 3
1 4 . 5 + - 0 . 3
2 4 . 4 t - 3 . 0
1 . 5 8 + - 0 . 0 4
2 2 . 4 + - 2 . 0
3 . 7 8 + - 0 . 0 2
4 . 5 0 + - 0 . 0 2
2 . 1 7 + - 0 . 0 3
1 3 5 + - 1 0
1 . 1 1 + - 0 . 0 2
0 . 7 6 < - 0 . 0 2
2 5 0 + - 1 5 0
0 . 8 5 » - 0 . 2 0
< 0 . 0 0 0 0 2
6 . 8 + - 0 . 8
0 . 0 7 2 * - 0 . 0 0 4
2
RESONANCEINTEGRALS
Ib)
8+-0.3
1 4 0 + - 2 8
2
1
8
1
4
4
2
2
1
1
10+-0.21
5»-0.4
1+-0.4
19+-0.06
13*-0.08
94t-0.10
32+-0.08
8+-0.2
401-0.05
77
2 5 . 2
0 . 2 4 4 - 0 . 0 3
6
6
6
6
6
6
6
64 5
6154
6314
6
6399
6
6
47432
4 0 9
3 9 5
3 2 4
102
23
430
10117
1 1312
1 1
1 1
4 7
58
RESONANCEINTEGRALS:REFERENCES
3 1 2
1 14 09
23313
2 3
13
1 0 9
1 1 9
339
12
123314
124
14
146
146
3 9 9
13
124321
145
4 1
156
156
4 3 2
14
128400
3 1 2
3 1 2
3 1 2
4 1
145
3 1 3
3 4 5
3 9 9
MAIN GAMMA RAYS FOR A* lNUCLIDE
ENERGY (keV)(ABSOLUTE INTENSITY:* )
366( 5 )
511(37)
1039( 8 )
91(7 )
1 1 16(51)
574( 100)
11 16(15)
1346( 0 . 5 )
93(16)
1482(23)
185(49)
z
TARGET NU
Z-SYMBOL-A
70
72
31-GA-NAT
69
71
72
32-GE-NAT
70
72
73
74
76
LIOE
ABUNDANCE IVOR HALF-LIFB
0.62
•46.SH
-
60
40
• 14. 1H
-
20.7
27.5
7.7
36.4
7.7
A*.
HALF-LIFE
56M
3.9H
2.4M
23.5S
-
21. 1M
36MS
14. 1H
4.8H
-
20MS
11.20
0.53S
-
48S
83M
54S
1 1 .3H
NUCLIOE
ISOMERSTATEIT IX)
G
M4G
MIT-0G
M4G
-
MIT•100
G
M+G
-
MIT=100G
MiG
MIT-100
G
MtG
MI T =99
G
M4G
MIT-19.8
G
M*G
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
IblAND
j(T) FACTOR
1.04-0. 1
1.072+-0. 100
0.00B7+-0.O005
0. 083»-0.005
0. 0924-0. 005
0.059
2.94-0. 1
1.68+-0.07
0.154-0.05
4.56t-0.23
4.714-0.23
4.25
2.34-0.2
0.28*-0.07
3.154-0.16
3.43*-0.2
0.98*-0.09
15.*-2.
0.17*-0.03
0.344-0.08
0.51*-0.08
0.104-0.01
0.06»-0.01
0.16*-0.02
RESONANCEINTEGRALS
Ibl
3.364-0.3
3.64-0.3
0.864-0.06
0.07
21.74-1 .5
15.54-1.5
"31. 14-2.9
25.7
6.04-1.0
1 .50
0.76
63.7
0.4 1 4 - o. 07
0.594-0.2
1.04-0.2
1.24-0.2
0.84-0.2
2.04-0.4
6
6
26
6
6
6
26
6
6
6
6
6
6
6
20
6
109
13
10
10
13
19
24
24
25
25
24
RESONANCEINTEGRALS:REFERENCES
409
11
11
24
26
26
92
29
26
57 312
57 312 399
26 32
32
32 92 312
32 92 312
MAIN GAMMA RAYS FORNUCLIDE
ENERGY IkcV)(ABSOLUTE INTENSITY:
386(93)122(3)
175(0.2)
630(25)
297(80)
140(34)199(H
215(26)211(29)
487(62)390(4)
1039(0.5)
834(96)
326(11)
265(11)
216(27)
512(28)512(32)
894( 10)
739<4)
264(51)
596(28)910(8)
2202(26)
768(1)
416(21)
A4 1
%)
620(57)1 120(2)
2508( 13)
1065( 1)
558( 15)
90Hto
TABLE II (cont.) t o
TARGET NUC
Z-SYMBOL-A
77M
G
MtG
3 3 - A S - 75
76
77
34-SE-NAT
74
76
77
78
79M
G
MtG
80
82
L I D E
ABUNDANCE HIOR H A L F -LIFE
•54S
•11.3H
1 0 0
•26.4H
•38.8H
-
0.9
9 .0
7.5
23.5
•3.9M
*6.5Et4Y
50.0
9 . 1
AH HUCLIDE
HALF-LIFE
88M
26.4H
38. 8H
1 .5H
-
12 0. 00
17.5S
-
3.9M
6.5Et4Y
-
-
-
57. 3M
IBM
69S
22. 4M
ISOMERSTATEIT IK)
-
MIT=IOO
G
MtG
MIT-100
G
MtG
MIT »99
G
MtG
M
G
MtG
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
Ib)AND
, ( T ) FACTOR
1 .48
4 . 4 8 4 - 0 . 1 1
6 0 . 8
12.69
11.7+-0.2
51.84-1.2
22t-1
634-7
854-7
42+-4
O.38+-O.2
O.05t-0.1
O.43+-0.2
3.28
0.084-0.01
0.53t-0.04
0.610+-0.045
0.0394-0.003
0.00524-0.0004
0.044t-0.003
RESONANCEINTEGRALS
Ib)
7 . 0 1
61-4
216. 1
68.25
12.6
514t-65
17+-2
23.3
40.3
324-3
3.74-0.6
1.064-0.80
4.76t-0.60
16.0
36—26
0.42 — 0. 1 1
1.28 — 0.32
1.704-0.30
O.OBt-0.04
26
653
432
26
26
6
2
6
6
6
6
6
32
26
6
6
6
1057
13
6
24
19
32
19
27
3 1 2
19
2 4
RESONANCEINTEGRALS:REFERENCES
11125
2 0
26
24
369
20
20
25
IB128
312
32
25
24
24
27
19312
3 4 5
26
25
25
24376
26
26
26399
27
27
MAIN GAMMA RAYS FORNUCLIDE
ENERGY (keVI(ABSOLUTE INTENSITY:
277(96)
559(45)
239(2)614
• (54)
121(17)
260(96)
357< 17)225
(32)
294(4)
657(6)
695(17)
136(59)
276100)
67 4(15)357
(69)
1213(2)
828(9)
265(59)
988( 15)510
(44)
1216(4)
1240(6)
280(25)
1030(21)718
( 16)
i t ,
1229(1 )
1309( 12)
401(12)
2051(11)799
(16)
o
In
35-8R-NAT ACT 6.9+-0.2 I91+-6 6 13 40
TARGET NUCL10E
Z-SYMBOL-A ABUKOANCf HIOR H A L F -
ILIFE
76
79
8 1
82M
G
M+G
36-KR-NAT
7 8
8 0
0 2
83
84
8 5
•16.2H
SO.69
49.31
•6 . 1M
'35.34H
-
0.35
2.25
11.6
11.5
57.0
• 10.76V
A«1 NUCLIDE
HALF-LIFE
57H
4.42H
18M
6. 1M
35.3411
2.40H
-
5 OS
34.911
13.3S
2. 1E*5Y
1 . fl3H
-
4 . 4 8 H
1 0 . 7 6 Y
-
ISOMERSTATEI T (%P
IT-100M
IT-100G
M+G
M
IT *97.6G
M*G
-
M
IT=100G
M'G
M
IT ** 100G
M i G
MI T - 1 0 0
G
M»G
Mi r -2 i .2
G
M«G
TYPEOF
REACTION
N.P
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
(b)AND
« ( T | FACTOR
224+-42
2.4+-0.6
8.6+-0.4
11.0*-O.7
2.431-0.4
0.26
2.7+-0.2
18.09
24.5*-3.5
0. 17*-0.02
6.03+-0.90
6.2+-0.9
4.55*-0 .65
6.95+-0.82
11.5«-0.5
14.0+-2.5
16+-10
30*-10
180*-30
0.090+-O.O13
0.042+-0.O04
0. 110+-0.O15
1,66t-0.2
RESONANCEINTEGRALS
(b)
3 5 . 7 * - 4 . 0
9 5 . 7 + - 1 0
131+-11
41 .3
8.9
50.2*-5.9
90.46
49+-4
20*-1
56*-7
190+-20
210*-30
2.4
0.8
3.2+-0.5
1.8*-1.0
6
6
6
3 4 7
347
626
432
26
6
6
6
6
634
25
25
6
6
23
23
10
1827
4 2 0
2-1
19
1938
19
24
RESONANCEINTEGRALS:REFERENCES
11
1928
3 4 8
24
24384
24
26
18
2038
4 2 0
25
25424
26
27
24
23312
26
26
27
28
4 3 2
24347
27
28
390
25399
28
38
MAIN GAMMA RAYS FORNUCLIDE
ENERGY IkeVI(ABSOLUTE INTENSITY
37(36)616(7)
698I 11\ t 1554
(71)
529(1)
261(13)
151(95)
666( 13)
776(8)619
(43)
300(2)
698(28)
306(3)
776(84)
398(9)
A * 1
%)
1317(27)
606(8)
s
TABLE II (cont.)ON
TARGET NUC
2-SYMBOL-A
86
87
37-RB-NAT
84
85
86M
G
M»G
87
88
38-SR-NAT
84
86
87
88
89
L1DE
ABUNDANCEl»lOR HALF-LIFE
17.3
•76.3M
-
•32.9D
72. 17
' 1.02M
•18.7D
27.83
'17.8M
-
0.56
9.9
7.0
82.6
•50.50
Atl HUCLIDE
HALF-LIFE
76. 3M
2.80H
-
1 .02M
18.7D
47E*9Y
17.8M
15.4M
-
67. 7M
64. 9D
2.81H
-
50.5D
28.5Y
ISOMERSTATEIT IV
-
MIT-100G
M+G
M
Q
MUG
-
MIT-87G
G+0.87M
M+G
MIT-99.7
G
G+M
TYPEOF
REACTION
ACT
ACT
ACT
N.P
ACT
ACT
ACT
ACT
ACT
ACT
ABS
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
(blAND
g(T) FACTOR
O.003+-0.002
<12600
0.35+-0.01
12t-2
0.053+-0.005
0.427+-0.011
0.48+-0.01
4.92
0.120+-0.030
1.0+-0.3
1 .28 + -0.06
0.60+-0.06
O.35+-0.07
0.87+-0.07
O.95+-0.07
0.84t-0.06
0.20»-0.03
1.04+-0.07
16+-3
0.058-1-0. 004
0.42*-0.04
RESONANCEINTEGRALS
Ibl
0.1+-0.On
'270
4.6+-0.4
1.744-0.10
3.76*-0.50
5.50t-0.50
33+-10
2.2+-0.3
10.0t-2.6
4.59*-0.15
6.6*-l.1
10.6*-1.1
1 1.2 + -1 . 1
4.79+-0.24
0.38
5.17
120*-15
0.06*-0.01
0.56<-0.22
6
27
6
312
228
24
6312
6
6
6
6
24
6
6
24
24
13
647
26
19
11
92
47
26
25
19
24
26
RESONANCEINTEGRALS:REFERENCES
26
40
1948
24
13
312
312
312
24
25
27
27 28
109
24 25 26 27312 345
25 26 27 28
17
25
26 27 28
MAIN GAMMA RAYS FORNUCLIDE
ENERGY (keV)(ABSOLUTE INTENSITY:
4 03(50)196
(26)
1077
(9)
898( 14)
658( 10)
151(95)514(98)
388(83)
845(7)835( 13)
1836(21)
1032(58)
2012 2555(3) (9)1530 2196(11) (13)
2678(2)
1248 2196(43) (13)
A*1
X)
2558(4)
2392(35)
2570( 10)
o7)•2H
E55a
TARGET NU
S-SVKIBOL-A.
90
91
39-Y - 89
90
91G
93
40-ZR-NAT
90
91
92
93
94
95
96
97
41-NB- 93
:LIDE A«l NUCLIDE
ABUNDANCE HII HALF-OR HALF- LIFELIFE |
'28.5V
•9.5H
100
•64.1H
'58.5D
•10.IH
-
51 .4
11.2
17. 1
•1 . 5E*6Y
17.5
•61.OD
2.8
• 16.8H
100
9.5M
2.71H
3. 19H
64. IH
49. 7M
58.5D
3.54H
19M
-
1 .5E»6Y
640
-
16. 8H
30.7S
6.2M
2.0E+4Y
ISOMERSTATEIT 1%I
MIT =99G
M*G
MIT-100G
M*G
-
M11-99.5
G
M+G
TYPEOFREACT1ON
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
0
0
0
1
1
THERMALCROSS-SECTIONS
(b)AND
j(T) FACTOR
.9»-0.5
. 148
.00H-0.0002
.279t-0.020
.28*-0.02
<6.5
1
0
0
0
1
0
2
0
0
0
0
1
.4+-0.3
.078
. 185*-0.003
.01U-0. 005
.24*-0.25
.220+-0.060
.6+-1.4
.0499+-0.0024
.49
.0229+-0.0010
.202
. 15+-0.05
RESONANCEINTEGRALS
Ib)
0.47+-0.07
0.62
0.85+-0.15
1.6
1 .4
3.0+-I.5
1.6+-0.5
0.99
1.18+-0.16
0.21+-0.09
6.8+-1.3
0.63+-0.11
2O»-IO
0.30+-0.07
6.5+-1.4
5.6+-0.9
1.55
8.2+-1.5
24
26
627
32
24
24
26
64 09
6365
6349
6
6
228
24
228
26
634
398
26
1028
26
26
10418
19
19357
19
19
638
26
638
1041
4 09
RESONANCEINTEGRALS:REFERENCES
27
1 140
27
11431
24
24365
24
24
1992
34
1992
1 157
432
28
1957
32
13
25
25
25
25
24312
384
24350
14312
24312
41
26
26
26
26
25350
25393
17352
25
45
27
27
27
27
26365
26
18353
26
365
32
28
28
28
27393
27
24354
MAIN GAMMA RAYS FORNUCLIOE
ENERGY (keV)(ABSOLUTE INTENSITY.
556(56)242(3)
448(2)550(6)
724(45)
355(2)
871( 100)7 03
(100M
653(8)431(3)
561(2)751(3)
757(55)
5 08(5)
871100)
750(24)953(4)
844(1)918(73)
1021( O
926(4)
1 142(3)
934(14)1139(7)
1 148(3)
A*l
X)
1024(33)1384(90)
1405(5)1669(3)
1750( D
s
TABLE II (cont.)0 0
TARGET NUC
Z-SYMBOL-A
94
9 5
42-MO-NAT
9 2
9 4
9 5
9 6
9 7
9 8
9 9
1 0 0
4 3 - T C - 98
99M
G
LIDE
ABUNDANCE HI!OR H A L F -LIFE I
•2.0E+4Y
•35 .15D
-
14.8
9 . 1
15.9
16.7
9 .5
24 .4
•66.OH
9 . 6
•4.2E<6Y
' 6 . OH
•2.1E+5Y
A+l NUCLIDE
HALF-LIFE
86 .6H
35.15D
23.4H
-
6 .9H
3.5E+3Y
-
-
-
-
66 . OH
-
14. 6M
6. OH
2.1E*5Y
15.8S
ISOMERSTATEIT (XI
M1 T - 9 7 . 5
G
M+G
-
MIT-99.8
G
M»G
MIT-99
G
M»G
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
IblAND
, ( T ) FACTOR
0.6+-0.1
I4.9+-1.0
20+-1.0
< 7
2.55+-0.05
0.019
0.015
14.0+-0.5
0.5+-0.2
2. 1+-0.5
0.13O+-0.006
1.733
0.199+-0.003
0.93t-0.2
1.67+-1.3
2 . 6 + - 1 . 3
1.62
2 0 * - 1
RESONANCEINTEGRALS
Ibl
I2O* - IO
24*-2
25*-1
0.81
0.86
108*-4
24t-4
15*-1
7.3*-1.8
26*-2
4.2*-0.5
26.7
230+-50
24
24
645
6
6
627
6
628
628
124432
24
628
358
26
6
352
26
1 1115
2 4
1428
19
15341834
147440
26
1834
400
15
RESONANCEINTEGRALS:REFERENCES
3 5 3
3 4
13117
1534
24
19384
1938
148
34
1940
432
26
384
14120
1940
25
24
2417
312
24109
27
17355
24384
26
25
2558
314
25117
28
404 09
25
27
26
261 17356
26124
4 0
4 1
26
27
27119400
27312
4 2 4
MAIN GAMMA RAYS FORNUCLIOE
ENERGY (keVI(ABSOLUTE INTENSITY:
7 6 6
( 1 00)
460(29)
41( D
192( 1 9 )
540( 7 )
669( 5 6 )
140( 5 )
506( 1 2 )
691( 6 )
778( 9 7 )
181( 6 )
591( 1 6 )
850(21 )
739( 1 2 )
696( 7 )
A + l
X )
1091( 4 9 )
778( 4 )
1012(13 )
o
H
ACT 2 . 5 7 + - 0 . 2 1 6 53
TARGET NU(
Z-SYMBOL-A
96
98
9 9
100
101
102
103
104
105
106
45-RH-103
104M
G
105G
•LIDS
ABUNDANCE I UOR HALF-LIFE
5.5
1.9
12.7
12.6
17. 1
31 .6
'39.350
18.6
•4.44H
•3680
1 0 0
•4.4M
M 2 S
•35.5H
A-H
HALF-LIFE
2.9D
39.350
-
4.44H
3680
3.8M
4.4M
42S
45S
35. 5H
45S
35.5H
2.2H
3 OS
NUCLIDE
IISOMERSTATE
I IT (XI
MIT=99.8
G
MiG
MIT-100
G
MtG
MIT-100
G
M«G
MIT»O
G
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
Ib)AND
j ( T ) FACTOR
0.29»-0.02
<8.0
7. U-1.0
5.01-0.6
3.4*-0.9
1 .2U-0 .07
7.71
0.32»-0.02
0.391-0.06
0. 1461-0.045
10+-I
1351-2
1451-2
8001-100
39.53
0.47
4 01-30
50001-1000
1 1000+-3OOO
160001-3160
RESONANCEINTEGRALS
Ib)
5 . 8 1 - 1 . 2
1661-20
1 1 .01-0.7
88*-17
4.6+-0.9
601-20
5.2* -0 .5
6.4*-1.4
1.8+-0.4
83*-6
9931-631076*-63
360
4.6
364.6
16500+-2500
0
6
6
634
690
24
6360
24
638
6
626
148
27
25
6360
3 1 2
24
24
15359
24109
26
24384
2 6
24361
147
1027
362
24364
RESONANCEINTEGRALS:REFERENCES
3 5 9
3 5 9
25
24384
25312
34
26
27
25372
148
1 128
384
25384
26
25
26359
3 8 4
27
3 4
26384
3 1 2
1540
389
26410
27
26
27384
2 8
3 8 4
27
3 6 2
1955
27
3 5 9
27
2 8
34
28
2496
3 4
28
34
312
34
25147
3 8
MAIN GAMMA RAYS FORNUCLIDE
ENERGV IkeVI(ABSOLUTE INTENSITY:
216(86)
497(89)
130(6)
194(11)
357( 13)358
306(5)
306( 5 )
451( 25 )
512(21)
325( 10)
610( 6 )
316( 1 H
374(4 )
74 1( 10)556( 2 )
319( 19)
319( 19)
512(87)622
( 10)
469( 17)
463( 4 )
759( 1 1 )
616(21)1050(2)
676( 15)
579(3)
768(77)
717(29)
A » l
X ,
724(47)
848(6)
1237(49)
1047(31)
46-PO-NAT IACT | 6 . 9 * - 0 . 4 11 40 53
TABLE II (cont.) totoo
TARGET NU
Z-SYMBOL-A
102
104
105
106
107M
G
108
109M
G
110
112
47-AG-NAT
107
109
LIDE
ABUNDANCE (HIOR H A L F -LIFE
1 .0
11
22.2
27.3
•21.3S
•6.5E*6Y
26.7
•4.69M
M3.46H
11.8
'20 .1H
-
51.83
48. 17
A*1 NUCLIOE
HALF-L1FE
17.0D
-
-
21.3S
6.5Et6Y
-
-
4.69M
13.4GH
-
-
5.5H
22M
1 .6M
-
127Y
2.41M
250 . ID
24. 6S
ISOMERSTATEIT 1%)
MIT=100
G
MtG
MIT-100
G
MtG
MIT=71
G
M+G
-
MI T - 8 . 5
G
MtG
MI T - 1 . 5
G
MtG
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
Ib)AND
9 ( T ) FACTOR
3 . 4 + - 0 . 3
0.6+-0.3
20*-3
0.013+-0.002
0.292+-0.029
0.305+-0.029
1.8+-0.2
0.183*-0.033
8.3*-0.5
8.483*-0.501
5.24
O.037+-O.O06
0. 190*-0.030
0.227+-0.031
0.29
63.3+-0.4G(T)=1.0034
0.33+-0.08
3 7 . 2 7 t - l . 2 0
37.6+-1.2
4 .7 * -0 .2G(T)-1.004886.3+-3.0
91.0+-1 .0
RESONANCEINTEGRALS
Ib)
10+-2
16+-2
83»-9
5.90+-0.53
77*-72.26+-0.04
224.74t-25.00
227+-25
60.6
0.6+-0.2
4.50+-0.63
5.1+-0.6
10*-5
748*-20
1 .26 + -0.19
93.74+-6.00
95+-6
72.8*-5.01377.2*-55.01450+-55
6
6
634
634
6
312
432
6312
26
6
24
25
6
6
6145
25425312
625
19
19384
19360
2 4
4 3 2
19
3 4
RESONANCEINTEGRALS'.REFERENCES
2 4
2 4
24384
26
24
3 1 2
25
2 6
1 134 0
4 2 5
10312
46426
1026
26
13363
1 1409
312427
1 127
26
25
25
27
25
27
14
24
351
1428
27
2 6
26
28
26
28
4 0
27
367
1534
27
27
34
27
312
45
34
3C8
1938
28
28
384
28
96
57
4 07
2440
MAIN GAMMA RAYS FORNUCLIOE
ENERGY (keV)(ABSOLUTE INTENSITY:
70(31)
434(99)434
658(96)658(5)
391(20)
614(98)619(9)
764(23)
575 633(12) (13)
723(99)633(2)
885 937(74) ( 3 5 )
A+1
X )
694( 7 )
1384( 2 5 )
oJO
E.
TARGET NU
Z-SYMBOL-A
110
111M
G
48-CO-NAT
106
108
109
110
111
1 12
113
1 14
1 15M
G
116
LIDE
ABUNDANCE IKIOR HALF-LIFE
•250.ID
•1 .2M
•7.50
-
1.2
0.9
M53D
12.4
12.8
24.0
12.3
28.8
•44.80
•53.38H
7.6
A*l NUCLIDE
HALF- llSOMERLIFE STATE
I IT (XI
1.2M
7.6D
3. 12M
-
6.5H
4B30
49M
-
14.6V
9.0E*15
44.8D
53.38H
-
-
3.31H
2.42H
MIT-99.7
G
M«G
-
MIT9100G
M+G
MIT»O.1
G
M*G
M
1 T = 0G
G*M
MIT-0G
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
N.A
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
Ib)AND
,(T) FACTOR
82*-l1
3+-2
2520»-50
1
1 . 1
700»-100
O.05
0. 14t-0.05
10.9
1 1*-1
24*-3
2.2»-0.5
20600+-400G(l)«!.3266O.036+-0.OO7
O.30*-0.02
O.336*-0.021
31.2
5.43
O.025 + -O.O1O
O.050+-O. 080
RESONANCEINTEGRALS
Ib)
41.3
105+-20
69.6»-5.7
4
1 1
2.5+-1
40.5+-7.5
53*-7
13.5»~1 .9
38S+-45
3.1+-1.5
19.9*-2.5
23+-2
195.9
79.9
0.422+-0.248
0.928*-0.514
343
25
6
3
6
6
6
6
6
6
19
25
629
24
26
398
4 09
25
6
24
29
19
19
19
24
398
19346
26
RESONANCEINTEGRALS:REFERENCES
38 408
4 09
398
24 26 27
24 25 26
24 26 27
26 27 28
24 25 26
398
27 28
28
34 384
27 28
MAIN GAMMA RAYS FORNUCLIDE
ENERGY (keVI(ABSOLUTE INTENSITY:
171(17)245(1)
607(3)
93(5)88
(4 )
934(2)261(2)
564(15)273(28)
245(71)342(7)
617(43)
336(16)
1029(12)344( 18)
507(6)
695(3)
492(8)
1066(23)434
( 10)
620(17)
1388(5)
528(27)
1433(13)1303(18)
A*1
%)
753(6)
1614(3)
1997(26)1577(11)
to
TABLE II (cont.)
TARGET NUCLIDE | A+l NUCLIDE
Z-SVMBOL-A ABUNDANCEl«!| HALF- 1S0MEROR HALF- LIFE STATEILIFE I I IT IX)
TYPEOF
REACTION
THERMALCROSS-SECTIONS
Ib)AND
g(T) FACTOR
RESONANCEINTEGRALS
Ibl
RESONANCEINTEGRALS:REFERENCES
MAIN GAMMA RAYS FOR A*!NUCLIDE
ENERGY (keV)(ABSOLUTE INTENSITY:*)
49-IN-NAT
113
115
50-SN-NAT
112
1 14
115
116
1 17
118
-
4.3
95.7
-
1 .0
0.66
0.35
14.4
7.G
24. 1
-
42MS
49.5D
7 1.9S
2.2S
54M
14S
-
2OM
1150
-
14. OD
-
-
2450
G+M
-
M2IT-100Ml
M14M2IT-=96.7
G
G4M14M2
M2IT-100Ml
MHM2IT-0G
G*M1+M2
-
MI T39 1G
G4 0.91M
G*M
MIT*100G
M«G
MIT=100G
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
0.0754-0.081
193.84-1.5
3.1+-0.7
S.0+-I.0
8.14-0.8
3.94-0.4
12.0+-1.1
814-8
81.34-8.0
162.3+-0.7
40+-2
202.34-2.0G(T)»1.O175
0.626+-0.009
0.304-0.04
0.714-0. 10
0.984-0.10
1.014-0.11
0. 1 15+-0.030
30+-7
0.0064-0.002
0.1344-0.030
0. 140+-0.030
2.34-0.5
0.0104-0.006
0. 21*-0.05
.35*-0.45
31334-75
220+-15
90t-33
3104-30
26054-115
655+-30
32604-150
6.4+-0.5
344-4
354-4
5.14-1.5
274-5
0.494-0.10
13.214-2.50
13.7+-2.5
15.74-2.1
1 .26
5.04
6
6
6
6
11312124
628129
6
6
6
6
6
6
6
25
25
24
13
109
10
23326374
10401S2
11
312
24
58
19
19
26
14
312
1 1
25373
1541266
13
398
26
312
24
24
27
40
371
24
124374
1960330
14
423
25
25
32
45
125
24123366
41
429
26
26
96
133
26124374
4 09
27
1
165
27125375
558( 102 ) (
558(13)
417(29)
1294( D
255(2)
725101)
819 1097 1294 2112(11) (56) (84) (16)
392(64)
o71
TARGET NUC
Z-SYMBOL-A
119
120
121M
G
MtG
122
123M
G
M t G
124
125M
G
MH)
126
51-SB-NAT
121
LIOE
ABUNDANCE HIOR H A L F -LIFE
8 .6
32 .8
'55Y
•27 . OH
4 . 7
'40.1M
•129.2D
5 . 8
•9.5M
•9 .640
'(1E+5Y)
-
57.3
A*l NUCL1DE
HALF-L1FE
-
55Y
27. OH
-
-
-
40 . 1M
129.2D
-
-
-
9.5M
9.640
( IE<5Y)
4.4M
2 . 1H
-
4.2M
2.7D
ISOMERSTATEIT 1X1
MtG
MIT-0
GMtG
MIT-0
G
MtG
MI T - 0
GM«G
MI T - 0
G
MtG
-
MI T - 1 0 0
G
MtG
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
Ib)AND
»<T> FACTOH
O.22t-0.052.2t-0.5
0.001t-0.0010. 140t-0.0300.141t-0.030
5.77
O.OOU-0. 001
O.180t-0.020
o. ieit-o.o2o
O.033
0.130t-0.005
O.004t-O.O02
0.134t-0.006
0.55
0.297
5. 1t-0. 1
0.06t-0.015 .8<n-o .2o
5 . 9 « - 0 . 2
RESONANCEINTEGRALS
Ibl
6 . 3 t - l . 5
4 . 2 t - 0 . 9
1 . 2 5 t - 0 . 3
26.29
O.84t-o.10
2.53
8.5t-0.80.032
8.532t-0.800
14.26
0. 195
170t-2013t-1
189t-i5
202+-15
6
6
6
26
6398
24
25
25
6
24
24
6
6
6
19
19
19
24429
26
92
24
26
2 6
12
10
RESONANCEINTEGRALS:REFERENCES
24
24
24
25
312
26
32
13
1 1
26
25
25
26
4 0 0
27
3 8
18
27
26
26
27
4 04
3 9 8
19
27
27
32 312
23 2-1
MAIN GAMMA RAYS FORNUCLIDE
ENERGY IkeVI(ABSOLUTE INTENSITY:
37(6)
160(86)
332(100 )
822( 4 )
22(1)
491(90)806(8)
564( 7 2 )
916( 4 )
23(7 )
1348(5 )823
(11)
693( 4 )
1067( 9 )
64( 10)
1564( 4 )859(8 )
1 141(31)
1089(4 )
87(9)
1096( 19)
A * 1
%)
2002(2 )
88(37)
1 1 14(38)
TABLE II (cont.) toto
TARGET NUC
Z-SVMBOL-A
122M
C
M+G
123
124
125
126M
G
M+G
127
128M
G
M*G
52-Tt-NAT
120
LIOE
ABUNDANCE III!OR HALF-LIFE !
•4.2M
•2.7D
42.7
•60.30
•2.77Y
•19.0M
•12.40
•3.85D
•10.4M
•9. OH
-
0.09
A*1
HALF-LIFE
-
-
-
2 0M
1.6M
60.30
2.77Y
19. OM
12.40
3.850
10. 4M
9.011
4.32H
-
1540
16.80
NUCLIDE
llSOMERSTATEIII 1%)
M2ITMOOMl
IT=80G
GfO.8Ml+ 0.8M2
G+M!*M2
MIT-14G
M*G
MIT-3.6G
MtG
-
MIT-90.2
G
TYPEOP
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
(b)AND
, <T) FACTOR
21.5
O.OI9*-O.O1O
0.037t-0.010
4. 1+-0.1
4. 145+-0.101
4. I56+-0. 10)
17.4+-2.8
0.97
5.81
0.92
1 . 14
4.7+-0.1
0.34+-0.06
2.0+-0.3
RESONANCEINTEGRALS
Ibl
159.0
128+-10
22.83
0.62
19.38
20
64.5
14.7
15.9
54-t-4
25312
26
238
6
9
32
24
24
26
26
6
26399
646
19
24
26
26
1 1
RESONANCEINTEGRALS:REFERENCES
27432
1048
24
26
27
13
38 47 60 92
11 18 23 2560 109 312 432
26 27
14
MAIN GAMMA RAYS FORNUCLIDE
ENERGY (keV)(ABSOLUTE INTENSITY:
498 603 646(99H100X100)603 646 723(98) (7) (11)
176 428(7) (29)414 620
(100) (2)(415 666(84)(1OO)(
252(8)314(95)314(61)
545( 18)
37(8)470(D
463( 10)666100)695100)
1 101(2)
1691(49)
601(18)695(96)697(29)
A+1
X)
2091(6)
636(11)1035(2)720(54)
412 473 686 784(4) (25) (35) (15)594 743 754 788(3)(100)(100) (7)526 636 743 754(45) (36)(100)(100)
684(12)
1 102(22)508
( 18)
813(43)
573(80)
915(20)
1030( 13)
TARGET NU
Z-SYMBOL-A
122
123M
G
124
125M
G
126
127M
G
128
129M
G
130
131M
L1DE
ABUNDANCE (WOR H A L F -LIFE
2 . 4
•119.70
0.87•12E*12Y
4 . 6
•68D
7 . 0
18.7
•109O
•9.35H
31.8
•33.60
•69.6M
34.5
•3011
A*l NUCLIDE
HALF-LIFE
119.70
12E+12Y
-
-
58D
-
1090
9.35H
-
-
33.60
69. 6M
-
-
3 OH
25. OM
78H
ISOMERSTATEIT IW
MtG
MIT"1OO
G
MtG
MIT-100
G
MtG
M
ITB97.6G
M>G
MIT=63.4
G
*HG
MIT=18
G
M*G
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
2 .
1 .
2 .
3 .
4 2
THERMALCROSS-SECTIONS
Ib)AND
, (T ) FACTOR
344-0.31
14-0.5
34-0.7
4*-0 .5
.89
418*-30
0.
6.
6 .
1 1
1 .
0 .
0 .
1 .
0404-0.025
764-1.31
8*-1.3
. 09
554-0.16
135+-0.023
904-O. 15
0354-0.15
33804-510
2 .
0.
0.
0 .
1 .
0 .
0.
0.
0.
0 .
76
0154-0.001
19971-0.0080
2M7J-0 .008!
11
37
024-0.01
274-0.06
29*-0.06
1 1
RESONANCEINTEGRALS
Ibl
6 4 * - 1 2
273 . 1
5547*-113
5 .94-1 .5
78.85
19+-3
1 .04
8.56
9 .64 -1 .6
11404-170
48.2
0.0774t-0.0050
1.54*-0.11
1.624-0.11
20.51
7.41
0.0485
0.446
0.494-0.05
0. 16
6
26
6
6
26
6
25
629
6
26
6
6
6391
24
26
25
25
632
26
19
19
19
19
19
24
370
25
19
26
20391
RESONANCEINTEGRALS.REFERENCES
24
24
24
24
24
26
3 7 0
24
24
25 26
25 26
26
25 26
25 26 27 28
26 27 28 29
26 27 28 29
MAIN GAMMA RAYS FORNUCL10E
ENERGY (keVI(ABSOLUTE INTENSITY:
5 8
(21 )
696( 9 )
774(50 )
150( 6 9 )
50( 14)
730( 2 )
794( 18)
452( 18)
1 12(2)
852(27)493(5 )
116(2)
1125( 15)6 02(4 )
228( 8 8 )
A * 1
%)
1207( 1 3 )1 147
( 5 )
Hto
TABLE II (cont.) toON
TARGET HU
Z-SYMBOL-A
G
132
53-1 -125
126
127
129
130
131
133M
G
M*G
135
54-XE-NAT
124
125
L1DE
ABUNDANCE(HIOR HALF-LIFE
•25.0M
•78H
•60.20
•12.BD
100
•1.6E+7Y
• 12.4H
•8.050
•9S
•20.3H
•6.68H
-
0.096
•16.8M
A+1 NUCLIDE
HALF-LIFE
55.4M
12.5M
12.8D
24.99M
9.0M
12.4H
B.05D
83.6M
2.3H
3.5M
52. OM
45. OS
84. OS
-
55. OS
16. 8H
-
ISOMERSTATEIT IX)
MIT-17G
MIT-83G
M4G
M
G
MtG
M
G
M<G
-
M
G
M»G
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
N.A
THERMALCROSS-SECTIONS
(b)AND
«(T) FACTOR
0.04
8944-90
5960
6.2+-0.2
18*-2
9t-l
27.0+-2.2
18+-3
0.7
0.003
0.022
23.9+-1.2
28+-5
137+-21
165+-20
<0.03
RESONANCEINTEGRALS
(b)
0.05
0.06
137304-2000
40600
1484-5
374-5
178
8.54-1.2
0.005
0.023
2624-45
6004-100
25454-650
3146+-645
26
24
6
6
6162340
627
24
24384
26
24
6
6
6
26
8
9
101724400
1528
26
25
26
35
RESONANCEINTEGRALS:REFERENCES
111825432
1630
32
26
34
36
12 1319 2026 27
19 2431 40
27 33
364
142128
25
34
152229
26
38
MAIN GAMMA RAYS FORNUCLIDE
ENERGY IkeVI(ABSOLUTE INTENSITY:
262( 14)312(71)
389(78)
443(17)
536( 100)
418(34)
80(3)175
(63)523( 16)
234(68)595(11)
197(78)1313(67)
55(6)
647(34)4 08(30)
491(7)
527(2)
586(7)536(99)
284(6)600100)630( 14)
847(99)622
(11)
864(29)(720(7)
666(59)
743(2)
1 122( D669(96)
364(81 )614( 18)(668(99)
884(99)847(95)
370 381( 17)(100)1321 2290(25) (11)
188(55)
243(29)
913100)787(6)
754(7)
1614(3)739(82)
637
668100)773(76)
884(65)
750(6)
24 15(7)
454(4)
A*l
X)
915( 19)1333( 10)
880(2)
1157(11)
723(2)773(99)955(18)
1073(15)
1313100)2634(7)
846( 1)
2
TARGET NUC
Z-SYMBOL-A
126
127
128
129
130
131
132
133
134
135
136
55-CS-133
134
LIDE
ABUNDANCE HIOR H A L F -LIFE
0.090
•36.410
1.919
26.44
4.08
2 1 . 18
26.89
•5.270
10.4
•9.14H
8.87
100
'2.05Y
A*l NUCLIDE
HALF- IISOMERLIFE (STATE
I I T l%l
75. OS
36.410
-
8.9D
-
1 1 .8D
-
-
2.260
5.270
-
15.6M
9. 14M
-
3.9M
2.89H
2.05Y
2.3E*6Y
MIT=100
G
M*G
MIT-100
G
HUG
M
G
M*G
MIT=100
G
M*G
MIT-99
G
M*G
MI T - 1 0 0
c
TYPEOF
REACTION
ACT
ACT
ACT
N.A
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
Ib)AND
) ( T ) FACTOR
0.45*-0.13
3.05+-0.81
3 . 5 * 0 . 8
<O.01
0.46*-0 . 10
6.02* -1 .5
6.5»-1 .5
21*-5
0.45»-0.10
6 + -1
6.45»-1
85+-10
O.O50+-O.O1O
0.400+-0.061
O.450+-O.O6O
190*-90
0.003*-0.001
0.262+-0.020
0.265+-0.020
(2 .65+-O.11) f *6
O.26»-0.02
2.5»-0 .2
29.0* -1 .5
140*-12
RESONANCEINTEGRALS
Ibl
8*-2
42*-15
50*-15
20*-10
85»-22
105*-20
252*-17
1 . 17
13.72
14.89
890+-120
0.9*-0.2
3.7+-0.6
4 . 6 ' - 0 . 6
356.3
0. 1
0.29
0.30
7475*-275
0.74+-0.21
30*-6
407*-24
422*-23
54.2
6
6
6
25
6
19
25
25
6
15
6
25
6
24
25
25
6
6
6
23
14
22846
6
37
25
24
24
25
24
26
24
19
24
29
19
63847
24
RESONANCEINTEGRALS:REFERENCES
26
26
3 5
2 6
2 7
26
24
2 6
432
25
134048
26
3 2
3 2
27
3 2
27
26
27
29
154150
27
28
34
28
27
28
34
2442
4 1 1
32
3 8 4
35
3 2
47
2643
412
39
34
432
2745
MAIN GAMMA RAYS FORNUCLIDE
ENERGY (keVI(ABSOLUTE INTENSITY:
58( 1 )
16412)
233( 10)
81(37)
787( 100)
250(90)
456(30)
569(15)
145(4)
1133(5)608(3)
605(96)
172126)
1358(5)
796(85)
203(68)
802(9 )
A * 1
375(17)
847100)
to
TABLE II (cont.) to00
TARGET NUC
Z-SYMBOL-A
135
136
137
56-BA-NAT
130
132
134
135
136
137
136
139
100
LIOE
A8UNDANCEIVOR HALF-LIFE
•2.3E+6V
•13.7D
•30.OY
-
0. 101
0.097
2. 42
6.59
7.81
11 .32
7 1 .66
•83.3M
•12.79D
A»1 NUCLIOE
HALF-LIFE
13.7D
3 0. OV
2.9M
32. 2M
-
11. 5M
11.60
391)
10. 5Y
29H
O.32S
2.6M
-
83. 3M
12.79U
IBM
ISOMERSTATEIT IX)
M
G
M+G
-
MIT-100
G
M*G
MIT-99
G
M<G
MIT=100
G
M+G
Mn-ioo
G
MlG
MIT=100G
M+G
TYPEOF
REACTIOM
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
Ib)AND
j(T) FACTOR
8.7+-0.5
1.3
0. 110*-0.033
1 .2*-0.1
2.5+-0.3
8.8+-0.9
11.3+-1 .0
0.5
6.5+-0.0
7.0+-0.8
0.I58+-0.024
i .844-1 .e
2.0+-1.6
0.0139+-0.0007
5.78+-0.90
5.8+-0.9
0.010+-0.001
0.39+-0.40
0.4+-0.4
5.1+-0.4
0.360+-0.036
6.2+-1.6
1 6+-0.3
RESONANCEINTEGRALS
Ib)
66+-B
44+-15
0.43+-0.15
9+-2
235+-25
3.3+-0.5
24t-4
13+- 1 1
37+-10
0.465+-0.070
I09.5+-17.0
110+-17
0.75+-0.04
0.85+-0.30
1.6+-0.3
4.8+-0.6
0.32+-0.07
13.2+-O.8
634
6
24
C
2
6
6
6
6
29
G
6
629
638
2449
24
26
1 1
6
29
29
24
24
19
19
20400
2451
RESONANCEINTEGRALS:REFERENCES
25384
26
27
13
29
32
25
25
24
2-1
244 09
25
26
20
17
47
26
25
?5
25
26
27
34
18
26
26
26
27
28
27
27
27
29
30
32
28
32
MAIN GAMMA RAYS FORNUCLIOE
ENERGY IkeVI(ABSOLUTE INTENSITY:
177( 14)
112(8)463(31)
124(29)
81(33)
268( 16)
662(90)
166(22)
30(11)190
(46)
341 818(49)(100)
192(81)547(11)
21G(20)
276(7)
163(6)277(23)
324(6)1010(30)
249(3)
303( 18)
305(4)304(25)
1048(80)
463(98)1436(76)
373( 13)
356(62)
424(3)344(14)
A«1
%)
1235(20)
1436100)2218( 15)
496(44)
384(9)
537(24)648(6)
z
TARGET NUC
Z-SYMBOL-A
57-LA-NAT
138
139
140
58-CE-NAT
136
138
139
140
141
142
143
144
59-PR-14 1
142
143
LIDE
ABUNDANCE<MOR HALF-LIFE
-
0.089
99.911
•40.22H
-
0. 193
0.25
•137.20
88.48
•32.50
1 1 .07
•33H
•284D
100
•19.2H
•13.59D
A«1 NUCLIOE
HALF-LIFE
-
-
40.22H
3.87H
-
34.4H
9. OH
55. OS
137.2D
-
32. 5D
-
33H
2840
3.0M
14.6M
19. 2H
13.590
17.27M
1S0MERSTATEIT (»>
-
-
MIT-99.2
G
M*G
MIT-100
G
M+G
M
G
M«G
TypeOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
Ib)AND
,(T) FACTOR
8.97*-0.05
57.2*-5.7
8.93»-0.04
2.7+-0.3
O.63*-O.04
0.95»-0.25
6.3*-1 .5
7. 25*- 1.52
0.015+-0.005
1.1+-0.3
1 .115+-0.300
500
0.57*-0.04
29»-3
O.95*-0.O5
6.0<0.7
1.0»-0.1
3.9*-0.3
7.6+-0.3
11.5+-0.3
20*-3
90<-10
RESONANCEINTEGRALS
Ibl
12.7*-0.8
548*-96
12.24-0.8
69*-3
0.67*-0.05
58+-12
0.48+-0.04
23.7+-4.5
1 . 14*-0.04
40
2.6+-0.2
17.8<-3.B
144
185+-15
1 1
6
22756
388
24
6
6
228
6
629
24
6388
62547
24
664
12
388
62857
399
25
13
388
629
24
2062
26
24
102652
26
24384
RESONANCEINTEGRALS:REFERENCES
52
428
152958
26
2047
26
24388
27
25
1127
384
32
25388
53
193459
27
2448
27
25
32
26
1228388
26
54
244060
38
2561
34
26
27
1529
412
27
55
2547
383
56
2662
384
27
39
1934
34
2648
384
388
27388
28
63
2440
38
MAIN GAMMA RAYS FORNUCLIDE
ENERGV (keVI(ABSOLUTE INTENSITY:
329(21)
1355(3)
169(27)447( 1 >
166(80)
145(48)
57(12)
80( D63
(15)
642(12)
696( 1)
487(46)
762( 15)
293(42)
134(11)284(9)
1576(4)
616(24)
825(34)
351(3)
440(6)
925(7)
835(8)
665(5)
724(59)
A-U
%)
1596(95)
1005(2)
722(5)
1 148(9)
3
TABLE II (cont.) too
TARGET NUCLIDE A*1 NUCLIDE
Z-SYMBOL-A ABUNDANCE ML HALF-OR HALF- L I F E
I L I F EF'*] IS0M6R
STATEIT 1%)
TYPEOF
REACTION
THERMALCROSS-SECTIONS
IblAND
,(T) FACTOR
RESONANCEINTEGRALS
Ib)
RESONANCEINTEGRALS:REFERENCES
MAIN GAMMA RAYS FOR A«lNUCLIDE
ENERGY |keV)(ABSOLUTE INTENSITY: \)
•5.98H 24.OM ACT 118.44 |445. 1 26
60-NO-NAT
142
143
144
145
146
147
148
150
61-PM- 146
147
148M
G
149
151
-
27. 13
12.20
23.87
8.29
17. 18
•11.060
5.72
5.60
•5.53Y
•2.62Y
•4 1.3D
•5.370
•53.1H
•28.4H
-
-
-
-
-
11.06D
-
I.8H
12M
2.62Y
41 .3D
5.37D
53. 1M
2.68H
15M
7.5M
4.2M
-
MIT-4.65
G
M*0
M2
M1
G
M2«M1+G
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
50.5+-2.0
18.7+-0.7
325+-10
3.6+-0.3
42+-2
1 .4 + -0.1
440+-150
2.5+-0.2
1.2+-0.2
8400+-1680
B5+-5
96t-2
181+-7
22000+-2500
2000*-1000
1400+-300
173
43.5+-5.5
8.5+-1.0
136+-35
5*-l
255«-40
2.7*-0.4
540*-150
14.0+-1.5
14.5+-2.0
1045+-265
)320*-85
2230^-70
3600-»-2400
43500+-4500
825+-50
1400*-400
6
6
627
6388
627
436
647
24
659
659
6
6414
634
388
6388
24
24
24
12
24
1428
24
1428
2462
26
2462
2462
25
254171540435
24
26
26
26
55
25
1534
25
1534
2565
34
2565
2565
34
38
1969
26
27
27
34
26
1940
26
1940
2666
384
2666
2666
G9
69
2470
27
34
34
384
32
24384
27
24384
27388
437
2767
27388
70
70
2672
34
69
384
388
25388
2B
25388
28
28388
28
388
71
2773
69
384
417
26
38
26424
29
29
29
414
388
28384
384
91(28)
1 14( 19)
117(47)
550(98)550
(23)
286(3)
334(69)
122(45)122
( 16)
319(2)
211(27)
139(8)
630(93)61)( D
832(12)
245(78)696( 1)
440( 1)
270(11)
175(8)
726(34)9!5(13)
876(7)
340(31)84 1(2)
531(13)
424(9)
256(17)
915(20)1465(22)
1 166(16)
1097(29)961(2)
541(8)
1 181(15)
1014(21)
1325(18)
1437(23)963(2)
o
•z>
TARGET NIK
Z-SYMBOL-A
62-SM-NAT
144
147
148
149
150
151
152
153
154
1 5 6
63-EU-NAT
151
152
153
154
LIDE A t !
ABUNDANCE l%ll H A L F -OR H A L F - L I F ELIFE |
-
3.16
15.07
11.27
13.82
7 .47
• 93Y
26.63
" 1 6 . 8H
22.53
*9.4H
47.77
52.23
•8.5Y
-
34 OD
-
-
93 Y
-
46 . 8H
-
23. SM
B.OM
96M
9.3H
12. 7Y
-
8.5Y
4.65Y
MUCL1DE
ISOMERSTATEIT <*l
-
M2
IT * 100Ml
IT-0G
IT-0G+MI+M2
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
IblAND
g ( T ) FACTOR
5800*-100
0.7
64 + -5
2.7*-0.6
41000*-2000G(T)=1.5860
102*-5
15000*-1800
206+-6
334.5
5.5<-1.1
17.16
4600+-100G(T)"0.90694.2*-2 .0
321l*-82G(T)«0.8936
5935»-73G(T)=0.90229146»-)09G(T)*0.8992
2313
603»-23G(T)"1.0290
15O0*-4OO
RESONANCEINTEGRALS
Ib)
I430+-120
650+-50
27t-14
3700*-400
280*-30
3100+-500
3960+-150
3700*-2000
29<-7
331.9
4346+-I70
1823*-146
35S2+-264
5367*-263
3414*-197
15OO»-450
6
634
424
674
676
634
418
628
102647
412
24
683
2 6
6
1086
48
659
62682
6442
13
1438
2475
1941 1
1974
1634
1 12779
432
26
24388
53
1487
59
1882
1 12783
24
RESONANCEINTEGRALS:REFERENCES
2440
26384
2 4
2476
1938
142880
34
26
55
2988
84
2483
142884
26
2575
27388
26
2577
24135
152981
3 8 4
2 7
8 4
58392
85
2784
152985
27
26384
2 8
27
26384
25384
183482
28
85
59
392
2985
1934
392
32
27387
3 4
28
27387
26388
1940
384
29
4 09
8 4
34392
2440
424
34
28388
3 8
3 4
2838B
27411
2441
388
8 2
8 5
53432
2553
3 8 4
MAIN GAMMA RAYS FORNUCLIDE
ENERGY IkeV)(ABSOLUTE INTENSITY:
61(12 )
70( 5 )
104(75)
122( 2 6 )
122(39)
123(40)
45( 1)
103(28)
)41(2)
344(3)344
(95)
185(20)
60( 1)
246(4)
842(52)779
(46)
723(20)
87(31)
963(43)964
(20)
1005(18)
105(21)
A»1
%>
1389(3 )
1408(29)
1274(35)
TABLE II (cont.) towto
TARGET NUC
Z-SYM80L-A
155
156
157
64-G0-NA1
152
154
155
156
157
158
159
160
LIOE |
ABUNDANCE IX)OR HALF-LIFE
•4.65Y
•15.4D
•15.1H
-
0.20
2. 15
14.7
20.47
15.68
24.9
• 18. OH
21.9
A H NUCLIDE
HALF-LIFE
15.4D
15. 1H
46M
-
242D
-
-
-
18. OH
-
3.7M
ISOMERSTATEIT (XI
-
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
Ib)ANO
g(T) FACTOR
4040*-125
480
190
49000»-1000
1 I 00*-100
85+-12
61000+-500G(T)»0.8387
1.5+-1.2
254000+-2000G(T)=0.8561
2.5+-0.5
16.3
0.77+-0.02
RESONANCEINTEGRALS
Ibl
1680+-300
1660*340
1350+-380
420+-15
3000+-300
280»-60
1570+-40
I00+-20
850+-100
80+-15
186.7
7 + -I
689
24
24
6
6
6392
689
678
678
647
56
689
24384
26
26
13
47
24
24384
2489
1989
2459
24392
RESONANCEINTEGRALS:REFERENCES
26442
28
34
78
89
25
26
2590
24384
2578
25
27
34
384
89
392
75
27
26392
26
2683
26
28
384
4 09
83
28
27
27
2789
32
34
89
34
28
28
28392
78
78
SO
78
75
34
29
83
MAIN GAMMA RAYS FORNUCLIDE
ENERGY IkeVI(ABSOLUTE INTENSITY:
89(9)
79(11)
70(2)
58(2)
56(5)
812(10)
898( 10)
97(28)
364(11)
102( 16)
1153(7)
944(25)
103(20)
283(7)
1231(9)
977( 14)
315(24)
Atl
%)
1242(7)
1108(4)
36(65)
65-TB-159
160
161
66-DY-NAT
156
158
160
161
100
•72.ID
•6.9D
-
0.0524
0.0902
2.294
18.88
72. ID
6.9D
7.48M
-
8. 1H
1440
-
-
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
23.2+-0.5
525*-100
96.6
1000+-40
33«-3
43 + -6
95+-10
510+-30
400»-25
1135
G55.9
1520+-80
960+-80
120+-20
1240+-140
1300«-100
228145
24
26
6
6
6
5
6392
629
392
26
93
97
97
6
19424
1847
432
32
94
12
24
1948
95
13
25
2462
96
95
26
2591
424
75
2692
96
87(13)
26(21)185
(16)
182(2)58(2)
299(27)
49(15)260(79)
326(95)
879(29)
57(2)808(45)
966(25)
75(10)882(12)
1 178( 15)
888(39)
oJO<
TARGET NU
Z-SYMBOL-A
162
163
164
165
67-H0-165
68-ER-NAT
162
164
166
167
168
170
171
69-TM-169
LIOE
•SUNDANCE HIOR H A L F -LIFE
25.53
24.97
28. 18
•2.35H
1 0 0
-
0. 136
1.56
33.4 1
22.94
27.07
14.88
•7.52H
100
AO NUCLIDE
HALF-LIFE
-
-
1 . 15M
2.35H
81 .5H
1200Y
27. 2M
-
75. 1M
10.34H
2.35S
-
9.6D
7.52H
49.511
0.004MS
130D
ISOMERSTATEIT (*l
MI T - 9 7 . 7
G
M4G
MIT-0
G
-
MITM00
G
M*G
M
IT•100G
M*G
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
IblANO
, | T ) FACTOR
245t-40
305+-25
1700»-250
1O00t-150
2700+-7S
3900'-300
3.5* -0 .5
61.2+-1.1
64.7* - 1 .2
162+-8
19t-2
13*-2
1S*-2
20*-2
35»-4
670»-30
1.95+-0.05
5.7»-0.2
280»-30
8+-1
95*-2
IO3»-3
RESONANCEINTEGRALS
(b)
2500t-250
1700*-200
650+-100
22000+-3000
55+-25
660*-35
715«-55
745+-25
480*-30
120*-10
125*-15
3000+-150
35*-5
24 + -4
1710+-70
6392
6392
686
424
6
18145
6
3
6
6
6
6
6
6392
6136
19424
19424
1995
97
25432
19
6
9 9
9 9
24
24
83
18432
19392
RESONANCEINTEGRALS'.REFERENCES
24
24
2497
29
24
9 1
3 9 2
3 9 2
75
83
99
29
29
25
25
2698
32
26
83
101
101
59
4 7
26
26
29145
47
55
101
136
136
83
9 1
75
75
34381
59
392
3 9 2
3 9 2
3 9 2
99
97
95
95
59392
142
409
136
102
MAIN GAMMA RAVS fOKNUCLIDE
ENERGY IkeV)(ABSOLUTE INTENSITY'
82( 13)
81(13)
81(6 )
112( 2 1 )
79( 3 )
184( 7 5 )
117( 2 )
84( 3 )
280 712( 3 0 ) ( 6 0 )
124 296( 9 ) ( 3 0 )
A* 1
X )
810(64)
308(66)
7)
to
TABLE II (cont.) N)
4
TARGET HUC
Z-SYMBOL-A
170
171
70-YB-NAT
168
W O
171
172
173
174
176
71- IU-NAT
175
176
L1DE
ABUNDANCE 1(1OR H A L F -LIFE
•130D
•1.92Y
-
0. 140
3.03
14.31
21 .82
16. 13
31.84
12.73
97.40
2.60
•3.3E10Y
A*1 NUCLIOE
HALF-LIFE
1 .92Y
63.6H
-
46S
31 .8D
-
-
-
67MS
4.20
6.5S
1 .9H
3.69H
3.3E 1 OY
0.160MS
155D
6.74D
ISOMERSTATEIT 1X1
-
MIT-100
G
NHG
Mn»ioo
GM+G
MU-100
G
M+G
MIT-0
G
M*G
Ml
M2IT-22
G
MHM2IG
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
Ib)ANO
» ( T ) FACTOR
92 + -4
4.5+-0.2
36.6+-2.0
3470*-100
1O»-1
50+-4
1.3»-0.B
19+-2
46*-4
19*-6
65+-5
2.4+-0 .2
77 + -3G(T)«1.496815. 10+-1.24
7*-1
2 2 . I + - 1 . 6
315+-60
2.1+-0 .7
1778+-75
2100*-50G(T)-1.6914
RESONANCEINTEGRALS
Ib)
460+-50
1 18*-6
195+-15
30500+-2500
270+-60
380t-45
25.2+-1.6
450»-55
34.5+-4.5
8. I+-1 .6
732+-63
523+-57
202+-30
725*-65
3.8«-1.0
1017+-45
6
6
6
6103
75
6
6
6
6103
6
6
29
6
3 3 9
6
136
136
9 1
2939?
83
75
75
75
29392
29
12
59
53
29
RESONANCEINTEGRALS:REFERENCES
103
4 7
103
B3
0 3
103
4 7
59
53
86
83
5 3
83
392
101
101
392
83
83
339
88
86
92
103
103
9 7
9 7
3 9 2
8 8
9 7
3 9 2
3 9 2
101
103
4 3 3
9 8
102
102
392
4 3 3
MAIN GAMMA RAYS FORNUCLIOE
ENERGY IkeV)(ABSOLUTE INTENSITY:
63( 4 4 )
114( 2 )
122( 3 )
88(9)88
(13)
113( 2 8 )
113( 6 )
1 10( 1 7 )
283(3)
139( 1 )
202( 8 4 )
2 08( 7 9 )
2 08( 1 1 )
177( 2 1 )
396( 6 )
150( 2 0 )
307( 93 )
228(48)
198(35)
1080(5 )
379(36)
A + i
%)
308(11)
1241(3)
419( 2 6 )
71
>
TARGET NU(
Z-SYMBOL-A
72-HF-NAT
174
176
177
178
179
1 8 0
181
73-TA-NAT
180
161
182
74-W -NAT
LIDE
ABUNDANCEHIOR H A L F -LIFE
-
0. 163
5.21
18.66
27. 1
13.75
35.22
•12.5D
-
0.0123
99.9077
• 115. ID
-
A<1 NUCLIDE
HALF-LIFE
-
7 00
-
4.3S
25 . 10
18.6S
5.5M
4 2 . 5D
61.5M
9E<6Y
-
-
16.5M
1 1 5 . I D
5.0D
-
ISOMERSTATEIT (XI
-
MH • 100
G
M*G
M21T-100
Ml1T=1OO
G
M*G
MIT-100
G
MtG
M
a
M*G
-
MI T m 1 0 0
G
MtG
-
TVPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
(b)AND
) ( T ) FACTOR
1 0 2 * 2
390*-55
38*-6
1 . H-0. 1
363*9
365*-20
53*-6
33*-8
86*-7
O.34*-0.03
44.66
45*-5
12.6*-0.7
40»-30
21.6»-0.7
700*-200
O.013*-0.003
21.5*-0.6
21.5*-0.6
8530+-45O
1 8 . 5 t - 0 . 5O ( T ) » 1 . 6 8 8 0
RESONANCEINTEGRALS
Ib)
2020*-65
288*-24
428*-55
7478<-244
1914+-95
4.75+-0.16
563+-55
568*-55
33.6*-3.2
717*-25
600*-200
0.415+-0.110
717+-25
717*-25
977t-58
352»-23
645
l «
6
6
G
6
29
6
94
3138
6
29
180
6112
2
3116
1094
2 9
94
94
94
94
6104
13142
339
432
10113
6
61 17
RESONANCEINTEGRALS:REFERENCES
1 1104
108
104
104
104
104
10105
14
3 9 8
1 1114
110
121 18
12105
105
105
105
105
1 1106
41
4 3 2
18139
1 14
13120
13106
106
106
106
106
29108
53
29144
180
144 09
14107
108
108
108
108
47109
1 10
47180
9 3
41108
4 8
1 1 ,
484 09
1 15
MAIN GAMMA RAYS FORNUCLIDE
ENERGY IkeVI(ABSOLUTE INTENSITY:
133(43)
1 14(12)
1 14(3)
68(41 )
108(11)
136(6)
340( I D
156(7)
100(14)
161(12)
137(2)
603(10)270
(80)
1121(35)
244(9)
346(14)
600(18)
1 189(16)
246(27)
A * !
X )
482(86)
943(37)
1221(27)
354(11)
>
H10
wI/I
TABLE II (com.)
TARGET NU
Z-SYMBOL-A
180
102
1 8 3
184
186
187
75-RE-NAT
185
187
76-OS-NAT
184
186
187
188
189
L1DE
ABUNDANCE HIOR H A L F -L I F E
0. 135
26.4
14.4
30.6
28.4
•23.9H
-
37.07
62.93
-
0.018
1.59
1 .64
13.3
16. 1
A + l
HALF-LIFE
1210
-
-
1 . 62M
750
23. 9H
69. 4D
-
88.911
18.7M
16. 7H
-
93.60
-
5.7H
10M
NUCLIDE
1S0MERSTATEIT 1X1
MI T - 1 0 0
G
-
MI T - 1 0 0
G
M*G
-
MI T - 1 0 0
G
M K i
MI T - 1 0 0
G
M»G
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ABS
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
Ib)AND
, ( T ) FACTOR
3 . 5
20.7*-0 .5
10.2+-0.3
0.002+-0.001
1.8*-0.2
1,8t-0.2
37.0+-1.5
64+-10
88.7t -3 .8
112<-3
7S + -4
1.6+-0.3
75>-4
15.3+-0.7
3005t-122
0.001
336*-17
4.31-1 .0
0.26+-0.03
22.74*-4.00
23 + - 4
RESONANCEINTEGRALS
Ib)
2 0 0
591+-45
367»-38
13.4+-2.5
49O'-15
2670+-550
82S+-36
1718+-45
8 .8+-0 .8
296.2+-10.0
305*-10
172»-35
1354+-52
89n*-100
135*-35
0.013+-0.001
750*-50
750+-50
6
6
6
6140
686
124400
6
6
6134
2 9
64 09
13
2 9
6
6
2 9
6
8 3
8 3
2 9
1093
125432
126
1 3 0
10137
10
5 3
146
RESONANCEINTEGRALS:REFERENCES
1 1 8
1 1 8
8 3
1 1116126
141
1 114 1
1 1
93 1 16
18 29118 121127 128
416
29 131409
29 132
118
58122129
132
137
121
83123143
133
141
MAIN GAMMA RAYS FORNUCLIDE
ENERGY tkeVI(ABSOLUTE INTENSITY:
72(11)
155( 15)
592(1)
134( 9 )
4 7 8
( 1 )
646(81 )
480(21 )
6 3 3( 1 )
717( 4 )
618( 6 )
875(7 )
A * l
X )
686(26 )
881(5 )
<
TARGET NUC
Z-SYMBOL-A
190
192
193
77-IR-NAT
191
192
193
78-PT-NAT
190
192
194
195
196
LIDE
ABUNOANCt { ( ]OR HALF-LIFE
26.4
41.0
•31.5H
-
38.5
•74.2D
61.5
-
0.0127
0.78
32.9
33.8
2 5 . 2
A4 1
HALF-LIFE
15H
151)
31 .5H
6.0Y
-
24 IV
1 .4M
74.20
17 ID
19H
-
3.0D
4.40
(BO)V
4 . ID
-
1 .5H
1811
NUCLIDE
ISOMERSTATEIT (*!
M
G
M»G
-
M2IT-100Ml
IT-99G
MtG
MIT-0
G
M4G
-
MIT=100
G
M'G
M1T-100
G
M i G
MIT»96.7
G
M«G
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
Ib)AND
g(T) FACTOR
13 .204 -0 .31
3 . 9 + - 0 . 8
17 . l t - 0 . 9
1 .974-0 . 11
1540
4264-4G ( T ) - 1 . 0 3 2 00.32* -0 .17
300+-30
6244-20
9244-53G(T) = 1.032611004-400
5 .84-2 .0
1104-15
112.54-7.5G(T) = 1.0218
10.04-0.2
1504-150
2 .24 -0 .8
< 14
0.0904-0.013
1.11
1.24-0.9
274-2
0.0504-0. 10
0.744-0.08
RESONANCEINTEGRALS
Ibl
2 6 . 5 4 - 2 . 5
3 1 . 7 4 - 2 . 5
58.24-3.7
5.4+-1.3
26064-120
10604-150
35354-250
45954-290
13624-33
1284-15
834-10
44-2
3554-50
8.34-2.0
29
29
6
6
6
147
29
6
6
6
6
6
6
6
146
29
13
148
86
10
10
11
29
RESONANCEINTEGRALSREFERENCES
146
53
11 46 147 148
11 29 86
14 41 142 4 09
57
MAIN GAMMA RAYS FORNUCLIDE
ENERGY IkeV)(ABSOLUTE INTENSITY:
129(26)
73(3)43
(2)
2 06(70)
328(93)294(3)
82(5)
130(3)77
( 17)
139(4)
308( 3 D
483(97)328
(13)
172(4)
202(1)191(4)
322(1)
316(87)
562(70)645(1)
360(6)
279(71)
387(1)
468(50)
600(62)
4 09(8)
A 4 1
* )
460(4)
485(67)
688(59)
539(14)
•vso
- 4
TABLE II (cont.) t
00
TARGET NUC
Z-SVHBOL-A
198
199
79-AU-197
198
80-HG-NAT
196
198
199
2 0 0
2 0 1
2 02
2 0 4
LIDE
ABUNDANCE(XIOR H A L F -LIFE
7. 19
•31M
100
•2.7D
-
0. 146
10.02
16.84
23.73
13.22
29.80
6.85
A * 1
HALF-LIFE
M S
3 I M
1 1 .5H
2.70
3. 150
-
24H
65H
43M
-
-
46 .90
5.6M
NUCLIDE
ISOMERSTATEIT l%l
M
IT"100G
M»G
-
MIT -93 .5
G
M+G
MIT-100
G
M»G
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
IblAND
«<T) FACTOR
0.0274-0.003
3.673
3.7+-0.2
1.5+-1.0
98.84-0.3G(T)-1.0038
267364-850
3754-5
1204-13
30804-200
32004-200
0.0184-0.004
1.8824-0.200
1.94-0.2
20004-1000
< 6 0
< 6 0
4.94-0.1
0.434-0. 10
RESONANCEINTEGRALS
(bl
5 5 . 6 4 - 2 . 5
15514-13
-(412404-4190)
734-10
58.94-2.4
4134-15
471.94-15.2
1.84-0.3
68.24-30.0
704-30
1534-30
4.434-0.25
0.804-0.04
6
2149
4 1 7
6
6
6
155
2 9
6
6
6
2 9
18
3150
1 1
29
29
29
RESONANCEINTEGRALS:REFERENCES
29 57 119 123 432
6 86 88 123 129151 153 154 409 446
12 13
155
155
46 155 156
MAIN GAMMA RAYS FORNOCLIDE
ENERGY (keVI(ABSOLUTE INTENSITY
77( 2 )
60( 2 )
412(95)
158(37)
130(?7
( 18)
279(81)2 04(2)
186(3)
76( 13)676(D
208(8)
202(D
317( 5 )
136(3 )
279(71)
494(6)
227(2)
A4 1
K )
543( 1 5 )
244( 3 )
o
81-TL-NAT
2 03
204
2 05
29.50
<3.78V
70.50
ACT
ACT
ACT
ACT
3.44-0 .5
11.0>-0.5
21.64-2 .0
0. 104-0.03
12.34-2.5
404-2
864-17
0.74-0.2
6
6
6
6
6
r>
9 6
10
10
1 l
157
1 1
1 1
14
102 157
40982-PB-NAT
2 04
ACT
ACT
0.1704-0.002
0.6614-0.070
0.164-0.05
1 .74-0 .5
TARGET NUCLIDE
Z-SVM80L-A ABUNDANCE 1*OR HALF-
ILIFE
206
207
208
83-BI-209
210
84-P0-210
25. 1
21.7
52.3
100
•5.01D
•138.40
A+1 NUCLIDE
HALF- llSOMERLIFE STATE
(IT (%l
3.3H
3.5E<6V
5.01D
2. 16M
25. OS
0.52S
MIT>0
G
M4G
MIT-0
G
TYPEOF
REACTION
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
ACT
THERMALCROSS-SECTIONS
IblAND
g(T) FACTOR
0.O305*-0.008
0.709*-0.010
0.487*-0.030
O.OI9*-0.002
0.0KH-0.003
0.033+-0.004
0.054+-0.005
< 0.0005
<O.030
RESONANCEINTEGRALS
Ib)
0 . 2 * - 0 . 1
0 . 4 t - 0 . 2
0 . 2 0 * - 0 . 0 6
0 . 2 0 * - 0 . 0 2
RESONANCEINTEGRALS:REFERENCES
6
6
6 11 14 41
158
MAIN GAMMA RATS FOR A*1NUCLIOE
ENERGY (keV)(ABSOLUTE INTENSITY:* )
266 305 650( 5 0 ) ( 2 8 ) ( 4 )
351( 1 3 )
85-AT-21 1
86-RN-220
222
87-FR-223
•7 .21H
•55 .6S
•3.8R
'22.OM
122M5
25. OM
4 3 . OM
2.7M
ACT
ACT
< 0 . 2
0 . 7 2 « - 0 . 0 7
63(8)
150 186 217 254 265( 6 ) ( 2 6 ) ( 3 ) <10) ( 5 )
8 8 - R A - 2 2 3
2 2 4
2 2 6
2 2 8
• 1 1
' 3 .
. 4 3 0
6 4 0
•1600Y
• 5 . 75Y
3 .
14
4 1
4 .
6 4 0
.8D
.2M
OM
ACT
ACT
ACT
ACT
130»-20
12.0*-0.5
1 1 . 5 » - 1 . 5G ( T ) > 1 . 0 7 0 836*-5
241( 4 )40
( 2 9 )27
( 17)277 284 300 3 0 3( 3 ) ( 3 ) ( 5 ) ( 5 )
Hto
8 9 - A C - 2 2 7 I - 2 1 . 7 7 Y I 6 . 1 3 H |ACT |762-»-29 I 159 160 209 338 911 965 969(5) (12) (29) (5) (17)
90-TH-227
228
18.7201 1.913Y
1.913Y
734 OY
FISS
FISS
200*-20
<0.3
123*-15
30.5»-3.0G(T)-1.049454»-C
>1O13
350»-B0
1000*-175
6
6 177 415
G
31 86 137 194 211(4) (3) (2) (5) (3)
TABLE II (cont.) toO
TARGET NUC
Z-SVMBOL-A
2 3 0
2 3 1
2 3 2
2 3 3
2 3 1
91-PA-230
231
232
2 3 3
LIDE
ABUNDANCE (VOR H A L F -L I F E
•8E44Y
•25.6M
100
•22.12M
• 2 4 . ID
• 1 7 . 4 0
•32500Y
• 1 .31D
•27.OP
A i l NUCLIDE
HALF-LIFE
25 . 6H
-
22.12M
2 1 . ID
6.9M
32500Y
1 .31D
2 7 . 0 0
1 . 17M
6.67M
ISOMERSTATEIT 1*1
M
IT = 0 .13G
M*G
TYPEOF
REACT1DN
ABS
FISS
ACT
FISS
ACT
ABS
FISS
ACT
ABS
FISS
ACT
ABS
F I S S
ACT
FISS
FISS
ACT
FISS
ACT
ABS
ACT
ACT
FISS
ACT
THERMALCROSS-SECTIONS
Ib)AND
j ( T ( FACTOR
8 4 . 5 4 - 6 . 7
<O.OOI2
2 3 . 2 + - 0 . 6
2 6 . 6 8
160. 1
186.78
(394-4)E-6
7.404-0.08
7.40+-0.08
15*-2
1500+-100
1515
<0.01
1 .84-0.5
I500+-200
0.0064-0.001G(T)-1.0670219+-6G(T)-1.03787004-100
464+-95
1 164+-135
21*-3
20*-3
<0. 1
4 U - 3GIT) = 1.0579
RESONANCEINTEGRALS
Ibl
13504-190
990+-40
156.2
837.6
993.8
0.0746+-0.0016
82.3+-2.4
82.44-2.1
84
408+-75
4924-75
0.0494-0.013
1 0404-40
2894-67
4254-33
4404-48
8054-35
6
4 09
4 09
4 0 9
1C4
6165207
3174
4 09
6
4 09
180
3
180
3 0
175
6415
161
4 09
1 1166239
13176
2 0 7
6
17B
184
3 8
RESONANCEINTEGRALS:REFERENCES
162
22167109
14235
4 0 9
1 8 0
184
175
163
29168415
22302
181
115
184
178
38169
454 09
182
186
4 1 5
17170
172
183
2 0 7
4 4 8
48171
173
4 4 8
3 8 5
MAIN GAMMA RAYS FORNUCLIDE
ENERGY IkeV)(ABSOLUTE INTENSITY:
26( 1 5 )
29(2 )
63( 4 )
150( 1 1 )
87( 2 )
131( 2 0 )
84(6)
86(3)
9213)
454(9)
300( 6 )
569( 1 4 )
459(1)
93(3 )
819( 7 )
312( 3 6 )
883( 12)
894( 2 0 )
340( 4 )
926( 1 1 )
A+1
%)
969( 4 2 )
416(2)
946( 12)
oJO><z>
TARGET NUCLIDE
Z-SYMBOL-A ABUNDANCE IVOR H A L F -
ILIFE234M
G
92-U -NAT
2 3 0
2 3 1
232
233
234
2 3 5
• 1 . I7M
•6.67H
-
'20.8D
' 4 . 3 0
«72Y
•162E+3Y
0.005•2.4E*5Y
0.720•7.1E + 8Y
A*I NUCLIDE
HALF-LIFE
23. 7M
-
4.30
72Y
I62000Y
247000Y
7.1E»8Y
239E-.Y
ISOMERSTATEJT |K)
-
TYPEOF
REACTION
FISS
FISS
FISS
ACT
ABS
FISS
FISS
FISS
ACT
ABS
FISS
ACT
ABS
FISS
ACT
ABS
FISS
ACT
ABS
THERMALCROSS-SECTIONS
IblAND
j ( T ) FACTOR
<5000
<500
4. W - 0 . 0 1
3 .35* -0 .02
7.S4+-0.02
25+-10
400t-300
G(T)-0.973973. 1+-1.5G(T)»0.9932147.1+-3.4G(T)«0.9836522.6+-2.8G(T)-0.9963
47.7+-2 .0GU1-1.0152
578.8+-2.0G(T).0.9977
<0.65
100 .2+- I .5
101+-2G(T)-1.OOI582.2+-1.3G(T)=0.9757
93.6+-1 .5G(T)"1.0052
680.8+-1 .3G(T)»0.9801
RESONANCEINTEGRALS
Ib)
34S+-35
280+-15
62B+-38
7 8 3 . 4 * - 7 . 8
1 3 8 . 1 + - 4 . 6
9 2 1 . 5 + - 9 . 1
5 .96
678+-38
684+-38
2 7 6 . 3 + - 2 . B
14 1 . 8 + - 4 . 2
4 1 8 . 1 * - 5 . 1
3
3
3
3189196204
3196415
3200
226
3415
228
3191207214
32 032184 09
32 09225
C
6
415
61901972 06
6197
38203
228
6
4 09
6193208215
6207221415
38210287
RESONANCEINTEGRALS:REFERENCES
180
182
38191199207
38200
192204
4 09
38
291962 09216
11209222
19321 1381
4 15
188
169192200260
190203
1932 07
2 07
38197210217
38210223
196212409
415
1801932014 09
192204
195409
2 2 7
8820321 1218
193212225
197214415
185194202415
193207
196415
2 2 8
124205212219
196214287
2 03218
187195203
1954 09
197
4 09
154206213220
197216381
207224
MAIN GAMMA RAYS FOR A* 1HUCL1DE
ENERGY IkeVI(ABSOLUTE INTENSITY: %)
109 144 163 186 205(1 ) ( 1 0 ) ( 5 ) ( 5 4 ) ( 5 )
>7)
TABLE II (cont.) toto
TARGET NUC
Z-SYMBOL-A
2 3 6
2 3 7
2 3 8
2 3 9
24 0
LIDE
ABUNDANCE IX)OR H A L F -L I F E
•239E»5Y
•6.7BD
99.275•451EWY
'23.5M
•14 . 1
A*l NUCLIDE
HALF-LIFE
6.75D
451E<7Y
2 3 . 5M
14 . !H
1S0MERSTATEIT (XI
TYPEOF
REACTION
FISS
ACT
ABS
FISS
ACT
ABS
FISS
ACT
ABS
FISS
ACT
ABS
FISS
ACT
ABS
THERMALCROSS-SECTIONS
IblAND
j ( T ) FACTOR
0 . 0
5 . 2 + - 0 . 3
5 . 2 + - 0 . 3G ( T ) - 1 . 0 0 7
2 .
41 1+-100
413+-100
<0.0005
2 . 7 0 + - 0 . 0 2G ( T ) - 1 . 0 0 9
2 . 7 0 + - 0 . 0 2
14 + -3
22 + -5
36«-6
0 . 0
1 .524
1 .524
RESONANCEINTEGRALS
Ibl
2
358t-8
360*-8
95.60
373.3
468.9
0.0013»-0.0002
276.3»-2.7
276.3+-2.7
264.2
156.6
420.8
1 .62
176.2
177.82
2 2 5
207
225234
2 2 6
6
2 2 5
397
3124238415
4 09
4 09
4 0 9
4 0 9
4 09
4 09
226
227
6228236
4 09
4 09
4 0 9
409
6168239419
RESONANCEINTEGRALS:REFERENCES
228 409
228 409 4 15
15 30 38229 230 2314 09
11 14 29207 217 218240 24 1 242
448
1 13232
38219287
217233
472374 09
MAIN GAMMA RAYS FOR A+1NUCLIDE
ENERGY (keVI(ABSOLUTE INTENSITY: %)
26( 2 )
44( 4 )
44
( 2 )
60 65 165 208( 3 3 ) ( 1 ) ( 2 ) ( 2 2 )
75(50) z
IP-
93-NP-234
2 3 5
236G
2 3 7
• 4 . 4 D
•396D
•129E+4Y
•214E*4Y
396D
22 . 5M
129E*4Y
214E+4Y
2 . 12D
MI I - O
G
M*G
FISS
ACT
ACT
ACT
FISS
FISS
ACT
ABS
900+-300
1600+-200
184+-4
1784
2500^-150
0 . 0 1 9 * - 0 . 0 0 3G ( D - 1 .0015169+-3G ( l 1 - 1 . 0 0 7 2169»-3G O 1 - 1 . 0 0 7 2
6 . 5 » - 1 . 2
8 2 1 . 5 + - 5 8 . 0
S28+-58
38
41
64 09
151 409
228 409 415 448
14 38 53 113 2?5 243
642( 2 )100(6 )
924( 3 )
104(8 )
984(24)
160(30)
1026 1029( 8 ) (17)
TARGET NU(
Z-SYMBOL-A
238
239
94-PU-236
237
238
239
24 0
:LIDE
ABUNDANCE HIOR HALF-LIFE
'2.I2D
•2.350
•2.85Y
•45.6D
•87.BY
'24390Y
'6450Y
A«l NUCLIDE
HALF-LIFE
2.35U
7.5M
65M
45.60
87.8Y
24390Y
6450Y
15Y
ISOMERSTATEIT l«l
M1T=.113
G
M*G
TYPEOF
REACTION
FISS
ACT
ABS
ACT
ACT
FISS
ACT
FISS
ACT
ABS
FISS
FISS
ACT
ABS
FISS
ACT
ABS
FISS
ACT
ABS
THERMALCROSS-SECTIONS
IblAND
S(T) FACTOR
22O0»-2O0
43
2243t-200
3 1*-6
14»-14
<1
45+-15
165*-20
33
195
240CH-300
16.5+-0.5
547+-20
564*-20
744.4+-1.7G(T)=1.0489
268.8+-3.0G(TI-1.1686
1013.2*-3.5G(T)-I.O8I2
O.O30+-O.O45
289.5+-1.4
289.53*-1 .41
RESONANCEINTEGRALS
Ibl
1454+-150
29
1483
960
197
1 157
24.2*-2.7
154+-9
178.2+-9.4
312.2+-8.2
191+-16
503.2+-18.0
5
8460*-305
8465+-305
6
38
3
226
226
6246
6247
6247
3197213252
3217261
32184 09
262
3243268
4 09
38
225
38
30247
38248
38249
6199216253
6218287
38243415
4 09
G261269
415
RESONANCEINTEGRALS:REFERENCES
225
226
225
384 09
2254 09
225250
38202217254
38243409
88246
415
14263287
243
243
243
225415
228415
228409
88203218255
88246415
203251
38264304
244
228
243
243415
154206243257
203251
207252
412654 09
243
245
245
1912 07246258
207252
216254
207266415
2-15
246
246
193208251259
216254
217287
228267
MAIN GAMMA RAYS FORNUCLIDE
ENERGY IkeVI(ABSOLUTE INTENSITY:
106(23)
263(1)
448( 18)
229(8)
104(4)
210(3)
3 03( 1)
566(29)
280(22)
149(8)
228(11)
555(22)
601(22)
299(16)
278( 14)
597( 12)
896( 14)
313(6)
A»l
*>
316(2)
818(D974(23)
321( 13)
>
CO
TABLE II (cont.)
TARGET NUC
Z-SYMBOL-A
24 1
2 4 2
2 4 3
244
245
95-AM-24 1
242Ml
G
2 4 3
LIOE
ABUNDANCEHIOR H A L F -L I F E
• 15Y
•387E43Y
•4.96H
'8.3E47Y
'10.5H
•433Y
' I52Y
•16.02M
•7370Y
A4 1 NUCLIDE
HALF-LIFE
387E43Y
4.96H
8.3E47Y
10. 5H
10.850
13. OS
152Y
16.02H
7370Y
26M
10. 1H
ISOMERSTATEIT (XI
M2
MlIT=9
G
M4G
M
I T a 0G
M4Q
TYPEOF
REACTION
FISS
ACT
ABS
FISS
ACT
ABS
FISS
ACT
ABS
ACT
ACT
ACT
ACT
ACT
FISS
ACT
ABS
FISS
ACT
ABS
FISS
ACT
ACT
FISS
THERMALCROSS-SECTIONS
IblAND
, ( T ) FACTOR
10094-8G ( T ) - 1 . 0 4 2 1
3684-10G(T)-1.0314
13774-10G(T)-1.0388
<0.2
18.54-0.4
18.74-0.4
180
87.4
267.4
1.74-0.1
1504-30
(104-5)6-5
83 .84-2 .6
7484-20
3.154-0 .10G(T)=1.02878324-20GU>"1 .0020836.15G(T)-1.002166004-300
14004-860
80004-800
29004-100
75 .24 -1 .8
4. 14-0.2
0.204-0.11
RESONANCEINTEGRALS
Ibl
5584-18
1614-13
7194-22
5
11314-57
11364-57
5 1 8
2 6 7
7 8 5
394-6
2204-40
2084-18
13304-117
2 1 . 5 4 - 1 . 7
15384-118
1559 .54-118 .0
22604-200
1 1004-000
33604-540
3 0 0
20894-11
1I1+-10
134-2 .5
32074 09
3246
3268
6
6
3276
2 7 3
2 7 3
2 7 3
6
6
6
6
6
228
228
6415
243
6
2 8 1
6
228
6208415
6268
3827 1
2 7 2
2 0 7
243277
4 09
4 09
4 09
2 7 9
243
243
2 2 8
281
278
243
246
243
4 1 5
113
272
RESONANCEINTEGRALS'.REFERENCES
38228
384 09
2034 09
2 7 3
2 2 8
245278
279
279
281
283
281
246
4 09
24G
422
273
191243
203415
207415
409
248
268306
281
281
301
409
409
284
279
301
197246
2 0 7
2 2 8
4 1 5
2 7 5
2724 09
282
282
4 09
415
415
286
4 09
4 09
202268
2 2 8
243
4 0 9
2 7 3
4 2 1
4 1 5
301
4 1 5
203270
243
2 4 6
4 1 5
274
434
4 3 4
4 09
4 3 4
MAIN GAMMA RAYS FOR ANUCLIDE
ENERGY IkeV)(ABSOLUTE INTENSITY:»
84( 2 3 )
308( 5 )
28( 4 )
49( 4 1 )
44( 5 )
99( 5 )
327( 2 5 )
44( 2 5 )
67( 5 )
75( 6 0 )
154( 18)
377( 3 )180
( 1 0 )
87( 8 )
746( 6 6 )
492( 3 )224
(23)
110(5)
900(27)
• 1
. )
560(5)
163(5 )
TARGET NUC
Z-SYMBOL-A
244M
G
96-CM-242
2 4 4
2 4 5
2 4 6
24 7
LIDE A4I NUCLIDE
ASUNOANCEIKII H A L F -OR H A L F - L I F ELIFE 1
•26M
• 10.1H
M63D
•28Y
' 17.9Y
•8.5E4 3Y
•4760Y
M54£*5Y
2.07H
28Y
17.9Y
8.5E43V
4760Y
154E + r>Y
3.5E45Y
ISOMERSTATEIT <«>
TYPEOF
REACTION
ACT
ABS
FISS
FISS
FISS
ACT
ABS
FISS
ACT
ABS
FISS
ACT
ABS
FISS
ACT
ABS
FISS
ACT
ABS
FISS
THERMALCROSS-SECTIONS
Ib)AND
) ( T ) FACTOR
7 9 . 3 » - 1 . 8
7 9 . 5 4 - 1 . 8GUI-0.9182
1600*-300
23004-300
5
16t-5
!K-S
6724-60
1364-10
810*-61
1 .24 -0 .1
13 .9 * -1 .0
15. 1
20204-40
3454-20
23654-45
0. 174-0. 10
1 .34 -0 .3
1 .474-0 .32
804-7
RESONANCEINTEGRALS
(bl
22004-15
22134-15
33
1564-35
1894-35
15274-142
214+-17
17414-143
1 3 . 4 4 - 1 . 5
632.64-32.0
646*-32
605+-80
101+-8
9064-80
1 1.34-1 .2
121 .34-7.5
132.64-7.6
7544-60
6281
113415
2 2 6
6
243
6
2 4 3
6
6273415
627344 1
228278
6293
6291
2434 09
64 09
6296
243438
6294
228306
228
243
226
4 09
243
4 02
243
228276
228276
243289
243294
2434 09
273415
243415
2434 09
2 7 3
243301
RESONANCEINTEGRALS:REFERENCES
2434 09
2 4 7
4 09
243
438
288
4 09
290
243278
243278
245290
272301
272415
27644 1
272
272415
2 7 6
2724 09
248415
2 7 3
2 7 9
2 8 9
4 0 9
245289
245279
246306
2734 09
273441
278
273
27344 1
278
273415
272422
2 7 6
4 09
4 02
246294
246289
2474 09
276415
2 7 6
2 7 9
2 7 8
2 7 9
306
278
273434
205
4 09
247301
2474 09
273415
2 7 8
2 7 8
2 8 9
2 9 4
2 8 9
4 09
2 8 9
2 7 4
4 0 9
4 3 9
2724 09
272415
276438
2 8 9
2 8 9
2 9 0
3 0 1
2 9 1
4 1 5
2 9 3
MAIN GAMMA RAYS FOR A+1NUCLIDE
ENERGY IkeVI(ABSOLUTE INTENSITY: X)
210(3)
133(5)
278( 3 )
228( I D
174( 5 )
287( 2 )
278( 1 4 )
346 402( 1 ) ( 7 2 )
s73H
TABLE II (cont.)
TARGET NUC
Z-SYMBOL-A
2 4 8
2 4 9
97-BK-249
2 5 0
98-CF-249
2 5 0
2 5 1
2 5 2
LIDE
ABUNDANCEl*lOR H A L F -LIFE
•3.5E*5Y
•64M
•311D
'3.22H
•350.6Y
• 13. IV
•900Y
•2 .63Y
A»l NUCL1DE
HALF-LIFE
64M
11300Y
3.22H
57M
13. 1Y
900Y
2.63Y
17.8D
ISOMERSTATEIT IW
TYPEOF
REACTION
ACT
ABS
FJSS
ACT
ABS
ACT
FISS
ACT
ABS
FISS
FISS
ACT
ABS
FISS
ACT
ABS
PISS
ACT
ABS
FISS
ACT
ABS
THERMALCROSS-SECTI0HS
IblAND
B ( T ) FACTOR
604 -15
1404-17
0.34t-0.07
4 + - 1
4 . 3 4 4 - 1 . 0 0
1 . 6 4 - 0 . 8
3
1300+-3
13034-300
9604-150
1676+-51
4924-28
21684-58
350
20304-200
23804-200
43004-300
28504-150
71504-350
324-4
20.44-1 .5
52.44-4.3
RESONANCEINTEGRALS
Ibl
650+-250
1404*-257
13.14-1.5
2754-75
288.14-75.0
5
1170*-80
1175*-80
2157+-70
7434-65
29004-96
85
1 16004-500
1 16854-500
54004-1500
16004-30
70004-1500
1104-30
43.54-3 .0
153.54-30.1
6415
2 4 3
6415
64 09
2 7 3
2 7 2
243
6
6301
6
2 4 3
2 7 2
2 4 3
6
6415
64 09
243
6415
6415
243415
243441
2 7 3
2 7 2
243415
2 7 8
2 7 3
272
273
2434 09
2 4 3
2 7 3
2 7 3
2 7 2
2 7 3
2 4 3
243415
2 7 3
2 4 3
2 4 3
2 7 3
RESONANCEINTEGRALS:REFERENCES
2 7 2
2 7 8
2 7 3
27244 1
4 09
4 09
273
276
273434
2 7 3
2 7 8
4 09
2 7 3
2 7 6
2 7 2
2 7 2
2 7 6
2 7 2
2 7 2
2 7 6
273 278
269 4 09
278 294
273 289
415 438
415
409 434
278 4 09
278 293
278 386
4 09
415
386 4 09
278 409
273 276
273 276
278 4 09
273 278
273 278
278 299
2 8 9
4 1 5
3 0 1
2 9 5
294
4 09
4 1 5
4 1 5
2 7 8
2 7 8
4 1 5
2 9 7
3 0 5
3 0 3
4 09
4 09
2 9 6
2 9 8
4 3 4
4 4 1
4 09
3 8 6
4 09
4 09
4 09
MAIN GAMMA RAYS FOR A4INUCLIDE
ENERGY (keVI(ABSOLUTE INTENSITY: X )
634(D
890( 2 )
177( 1 8 )
929 989 1029 1032( 1 I ( 4 5 ) ( 5 ) ( 3 6 )
227 285( 6 ) ( 1 )
ow
>
n
TARGET NU
Z-SYMBOL-A
253
254
99-ES-253
254M
G
255
100-FM-254
255
256
257
LIDE
ABUNDANCE I I IOR H A L F -LIFE•17.80
•60.5D
•20.470
•39.3H
•276D
•390
•3.24H
•20.1H
•2 .63H
•100 .50
A*l NUCLIOE
HALF-LIFE
60. 5D
39.311
276D
390
20. 1H
2.63M
100.50
0.38MS
ISOMERSTATEIT <%l
MIT»O
0
M«G
TYPEOF
REACTION
FISS
ACT
ABS
FISS
ACT
AGS
ACT
ACT
FISS
ACT
FISS
ACT
ABS
FISS
ACT
ABS
ACT
ACT
FISS
ACT
ABS
ACT
FISS
ACT
ABS
THERMALCROSS-SECTIONS
IblAND
j ( T ) FACTOR
1300<-240
17.6<- 1 .8
13I7.6*-24O.O
2
88*-30
90»-30
• 55<-20
3
O.O
I58*-2O
1840t-80
1 .3
184 1.3
2830*-130
4 0
2870+-I3O
43*-10
7 6
3400*-170
26*-3
3426*-170
45
2950»-16O
3150
6100*-6OO
RESONANCEINTEGRALS
Ibl
2117
13
2130
28
1650
1678
3009* -168
4299+-216
0 .0
7308*-275
1000
2200+-90
5000
RESONANCEINTEGRALS:REFERENCES
272 273 278 415
272 273 278
273 278
272
272
278
6 256
6 256
273
256
256
6 300
4 0 1
MAIN GAMMA RAYS FOR A«1NUCLIOE
ENERGY (IteVI(ABSOLUTE INTENSITY:* )
71 177 212 649 694(13) (17) (29) (29) (25)
63(2 )
81
( 1 )
62 179 241(11 (9 ) ( 10 )
SO
248 GRYNTAKIS et al.
5. EXPLANATION OF THE COLUMNS IN TABLE II
Column 1 - Atomic number, symbol and mass number of the target nuclides.M signifies a metastable state and G the ground state.
Column 2 — Per cent abundance of natural nuclides. Data with an asteriskrepresent the half-lives of radioactive nuclides.
Column 3 - Half-lives of A -I- 1 nuclides.Column 4 - Metastable state (M), ground state (G) and per cent internal
transition (IT) of the upper to the next lower state, taken inmost cases from Ref. [310].
Column 5 - Type of thermal cross-section and resonance integral.Column 6 — Thermal cross-sections at 2200 m/s neutron velocity
(Eo = 0.0253 eV). For the non-l/v nuclides, the g(Tn = 20°C)Westcott factor is also given.
Column 7 - Resonance integrals I (from Ec = 0.5 eV), including the1/v contribution.
Column 8 - References for the resonance integrals.Column 9 — Main gamma rays and their absolute intensities, taken in most
cases from the Evaluated Nuclear Structure Data File library[447] and from the Table of Isotopes [310].
ACKNOWLEDGEMENTS
The authors are grateful to H. Lemmel and K. Okamoto of the NuclearData Section of the IAEA for their assistance and co-operation in the preparationof this compilation.
REFERENCES
1 . E.M. GRYNTAKIS, J. I .KIM, J . RAD1OANAL .CHEM. ,76( 1983)341 .2. A.AHMAD,ANN.NUCL.ENERGY,10(1983)41.3. M.K.DRAKE.NUCLEONICS.24( 1966)NO.8.108.4. H.ALBINSON,IAEA.TECHNICAL REPORTS SERIES NO.156,VIENNA.1974 P.15.5. P.RIBON,J.KREPS.73 BOLOGNA,REVIEW PAPER NO.10(1973) OR IAEA-169,
FISSION PRODUCT NUCLEAR DATA,1(1974)235.6. NEUTRON CROSS SECTIONS.BNL-325.3RD EO..VOL.1, 1973.AND VOL.1PART A.1981.7. CINDA 79,IAEA,VIENNA.1979.8. M.BRESESTI, A.M.BRESESTI DEL TURCO. H..NEUMANN.E .ORVINI . J . INORG . NUCL .
CHEM.,26(1964)1625.9. M.F.ELGART,THESIS,CITY UNIV.OF NEW YORK,1971.UNIV.MICROFILMS ORDER
NO.72-988.DA/B32.3245,1971 .10. S.P-HARRIS.C.O.MUEHLHAUSE.G.E.THOMAS.PHYS.REV..79(1950)11.11. R.L.MACKLIN.H.S.POMERANCE.PROC.CONF.PEACEFUL USES OF ATOMIC ENERGY.
GENEVA,5(1956)96.12. P. E.SPIVAK.B.G.EROZOLIMSKY.V. I. LAVERENCHIK . PROC .CONF . PEACEFUL USES
OF ATOMIC ENERGY,GENEVA,5(1956)91.13. V.B.KLIMENTOV.V.M.GRIAZEV. J.NUCL.ENERGY,9( 1959)20.TRANSL. FROM AT.
ENERG. (USSR)3(1957)507.14. R. B. T ATTERS ALL. H. ROSE. S.K.PATTENDEN,D.JOWITT,J. NUCL. ENERGY. 12( 1960)32
PART 2-1 249
15. E.A.NEPHEW,REP.ORNL-2869.REACTORS-POWER TID-4500(15TH E D . ) . 1 9 6 0 .16. N.J.PATTENDEN.NUCL.SCI.ENG.,17(1963)371.17. YU.A.PROKH0R0V.INDSWG-64,1964,P.75.18. OFFICE OF ATOMIC ENERGY FOR PEACE,BANGKOK. CERTAIN ACCOUNTS ON THE
UTILIZATION OF THE THAI RESEARCH REACTOR.BANGKOK CONF.REP.THAI-AEC-10,1967.
19. M.A.PALMUCCI.COMITATO NATIONALE ENERGIA NUCLEARE,RT/FI(67)4.ROMA.196720 . M.D.RICA8ARRA.R.TURJANSKI.G.H.RICABARRA.C.B.BIGHAM, CAN J.PHYS..46
( 1968)2473.21 . D.BRUNE.RADIOCHIM.ACTA,12(1969)119.22 . L . BREITENHUBER.H.HEIMER.M. PINTER. ATOMKERNENERGIE, 15( 1970)83 (SEE ALSO
EANDC(OR)-68.1968.P.10).23 . T.B.RYVES. J.NUCL.ENERGY.24(1970)35.24 . R.E.SCHENTER, PRIVATE COMMUNICATIONS TO NEA/DATA BANK, CALCULATIONS
FROM ENDF/B-IV LIBRARY.HANFORD ENG. DEVELOPMENT LABORATORY,RICHLAND,WASH.USA,1975.
25. W.H.WALKER,AECL-3037,PART 1,1972.26 . E.CLAYTON,AUSTRALIAN AEC,REP.AAEC/TM619(1972).27 . H. H. SAK ATA. S.NAGAYAMA, JAP. ATOMIC ENERGY RESEARCH, TOKAI . UNPUBLISHED
(SEE REF.5) .28 . G.LAUTENBACH,REP.RCN-191.1973.29 . R.VAN DER LINDEN,F. DE CORTE.J.HOSTE.J.RAOIOANAL.CHEM. ,20(1974)695
(SEE ALSO 73PARIS, IAEA,2(1973)241.3 0 . T . A . E ASTWOOD, A. P . BAERG. C . B. BIGHAM. F . BORWN. M. J . CABELL , W. E . GRUMMITT.
J.C.R0Y,L.P.R0Y.R.P.SCHUMAN.2N0 PROC-CONF.PEACEFUL USES OF ATOMICENERGY,IAEA.GENEVA,16(1958)54.
31 . J.C.ROY.D.WUSCHE,CAN.J.CHEM..36(1958)1424.32. T.R.ENGLAND.WAPD-TM-333.1965.33. J.HALPERIN.R.E.DURSCHEL.0RNL-3488.1963,P.15.34. A.L.POPE,AEEW-M-1266.1974(SEE ALSO AEEW-M-1234,1973 AND AEEW-M-1191.
1973).35. T. A. E AS TWOOD. F. BROWN, EANDC( CAN),16(1963)6.36. M.BRESESTI.F.CAPPELANI.A.M.DEL TURCO.E .ORVINI. J . INORG. NUCL .CHEM. ,26
(1964)9.37. M.BRESESTI.F.CAPPELANI.A.M.DEL TURCO.H. NEUMANN.E .ORVINI. J . INORG.NUCL.
CHEM.,27(1965)1175.38. 0. J.EDER.M.LAMMER. NUCLEAR DATA IN SCIENCE AND TECHNOLOGY . IAEA . 73PARIS
1.1973.P.233.39. E.S.STIPPEL.0RNL-TR-1365,1965.40. J.D.GARRISON.B.W.ROOS.NUCL.SCI.ENG..12( 1962)115.41. H. ROSE. W. A. COOPER, R.B.TATTERSALL. 2ND PROC . CONF . PEACEFUL USES OF
ATOMIC ENERGY,IAEA.GENEVA.1(1958)16.42. A.P.BAERG,R.M.BARTHOLOMEW.CAN.J.CHEM.,38(1960)2528.43. F.BROWN.P.J.CAMP ION,B.H.OLIVER,J.NUCL.ENERGY,13A(196 1 ) 14 1 .44. R.VIDAL.E.CARDOSO-MARTINHO.CEA-R-2840.1965 (SEE ALSO CEA-R-2486.
1964 AND REF.45).45. J.C.CARRE.R.VIDAL,NUCLEAR DATA FOR REACTORS . IAEA. 66PARIS . 1 ( 1966 )479
(SEE ALSO REF.44,68).46. G.H.E.SIMS.D.G.JUHNKE.J.INORG.NUCL.CHEM.,30(1968)349.47. E.STEINNES.J.INORG.NUCL.CHEM.,34(1972)2699.48. A.ALIAN.H.-J.BORN,J.I.KIM,J.RAOIONAL.CHEM.,15(1973)535.49. A.P.BAERG.F.BROWN.M.LOUNSBURY.CAN. J.PHYS.,36(1958)863.50. H.M.EILAND.F.B.FEHR.E.C.HANSEN, J.L.MEWHERTER.KAPL-2000-1 1 , 111-30. 196051 . J.HALPERIN.J.S.ELORIDGE.H. A.O'BRIEN. JR. , R .E -DRUSCHEL .ORNL-4164 . 1. 196752. V. A. KONKS.YU. P. POPOV, F.L. SHAPIRO. J . EXPERIM. THEORET . PHYS . ,46( 1964)80.53. J.W.ROGERS.J.J.SCOVILLE.TRANS.AM.NUCL.SOC. . 10( 1967)259(SEE ALSO REF .
55) .54. H.SHWE.R.E.COTE,W.V.PRESTWICH,PHYS.REV..159(1967) 1050.55. J.J.SCOVILLE,J.W.ROGERS.IN-1195.1968 (SEE ALSO REF.53).56. H. A. O'BRIEN. JR. , J . S -ELDRIDGE ,R.E .DRUSCHEL . J .HALPERIN, J . INORG. NUCL .
CHEM.,29(1967)584.57. T.B.RYVES,J.NUCL.ENERGY.25(1971)129(SEE ALSO REF.304).58. F.DE CORTE.A.SPEECKE.J.HOSTE.J.RADIOANAL.CHEM.,9( 1971 )9.59. E.STEINNES.J.INORG.NUCL.CHEM.,37(1975)1591.60. E.ORVINI.G.GAGGERO.L.LESCA.A.M.BRESESTI.M.BRESESTI , J. INORG. NUCL.
CHEM..30(1968)1353.61 . P.M.LANTZ,C.R.BALDOCK,L.E.IDON,NUCL.SCI .ENG. ,20( 1964)302(SEE ALSO
TRANS.AM.NUCL.SOC..6(1963)44).62. J.ALSTAD.T. JAHNSEN.A.C.PAPPAS.J.INORG.NUCL.CHEM. ,29( 1967 )2155(SEE
ALSO INDC(NOR)-1/G.1972.P.1).63. P.M.LANTZ.NUCL.SCI .ENG..13(1962)289.64. J.C.ROY.L.P.ROY,CAN.J.PHYS.,37(1959)907.65. J.I.KIM,E.M.GRYNTAKIS,RADIOCHIM.ACTA,17(1972)191.66. M.D.RICABARRA.R.TURJANSKI.G.H.RICABARRA, CAN. J.PHYS. ,51 ( 1973)1454.67. C.P.RUITZ,J.P.PETERSON.JR.,B.F.RIDER.TRANS.AM.NUCL.SOC.,7( 1964)270.68. R.VIDAL.EANDC(E)-57,1965.P.170(SEE ALSO EANDC(E)-57,1965.P. 171
AND REF.45).69. R.P.SCHUMAN,J.R.BERRETH,NUCL.SCI.ENG. .12( 1962)519.70. N.C.FENNER.R.S.LARGE,J.INORG.NUCL.CHEM..29(1967)2147(SEE ALSO
EANDC(UK)-75-5.1966).71. M.J.CABELL.J.INORG.NUCL.CHEM..32(1970)3433.72. J.E. CODDING. JR. . R . L . TROMP .F . B .SIMPSON, NUCL .SCI .ENG. ,43( 1971)58.
250 GRYNTAKIS et al.
73 . G . J . KIROU AC , H. M. E I LAND. C . A. CONRAD, R . E . SLOVACEK , K . W. SEE MAN. NUCL .SIC.ENG.,52(1973)310.
74. H.M.EILANO.S.WEINSTEIN.K.W.SEEMAN,NEUTRON CROSS SECTION AND TECHNO.,PROC.OF THE 3RD CONF.(CONF-710301)0F UNIV.OF TENESSEE.KNOXVILLE.1971.P.673.
75. R.DOBROZEMSKY.F.PICHLMAYER.F.P.VIEHBOECK. INTERN. J. MASS SPECTROM. IONPHYS.,6(1971)435(SEE ALSO REF.100).
76. K. L.AITKIN.F.W.CORNISH,J.INORG.NUCL.CHEM. .17(1961)6.77 . J . HAL PER IN, R. E . DRUSCHEL , C . R . BALDOCK , TRANS . AM. NUCL . SOC .,5(1962)376 .78. S.F.MUGHABGHAB.R.E.CHRIEN, PHYS. REV. , 180( 1969)1 131 .79. W.H.WALKER.R.E.GREEN,CAN.J.PHYS.,39(1961)1184.80. R.E.CHRIEN.CAN.J.PHYS..39(1961)1193.81 . M.S.CABELL.J.INORG.NUCL.CHEM.,24(1962)749.82. F.J.RAHN,C.HO.TRANS.AM.NUCL.SOC..12(1969)749.83. F.J.RAHN,H.S.CAMARDA.G.HACKEN.W.W.HAVENS,JR. ,H.I.LIOU.J.RAINWATER .
M.SLAGOWITZ.S.WYNCHANK.NUCL.SCI.ENG..49(1972)219.84. G.H.E.SIMS.O.G.JUHNKE,J.INORG.NUCL.CHEM.,29(1967)2671.85. J.I.KIM.E.M.GRYNTAKIS.H.-J.BORN.RADIOCHIM.ACTA,22(1975)20.86. P.P.DAMLE.A.FABRY.H.VAN DEN BROECK.BLG-421.CEN-SCK,MOL(1967).87. F.V.ORESTANO.F.PISTELLA.NUCL.SCI.ENG.,37(1969)478.88. A.GIBELLO.F.V.ORESTANO.F.PISTELLA.E.SANTANDREA.NUCL.SCI.ENG..40
(1970)51.89. S. J.FRIESENHAHN.M.P.FRICKE,D.G.COSTELLO,W.M.LOPEZ.D.CARLSON,NUCL.
PHYS.,A146(1970)337.90. P.M.LANTZ.C.R.BALDOCK.L.E.IDOM.ORNL-3832.1965.P.7.91. J.J.SCOVILLE.J.W.ROGERS,TRANS.AM.NUCL.SOC.,8(1965)290.92. G.H.RICABARRA,R.TURJANSKI,M.D.RICABARRA,CN-26/1,1970(THE SAME AS 70
HELS.2(1970)589).93 . J . J . SCOVILLE,D.W.KNIGHT.E.FAST,TRANS.AM.NUCL.SOC..5(1962)377.94. J.J.SCOVILLE.E.FAST.D.W.KNIGHT,NUCL.SCI.ENG..18(1964)400.95. J.J.SCOVILLE.E.FAST.J.W.ROGERS,NUCL.SCI.ENG.,25(1966)12.96. G.HUETTEL.KERNENERGIE,!4(1971)73.97. J.ALSTAD.A.C.PAPPAS.T.SYVERSEN.INDC(NOR)-1/G,1972.P.2.98. W.L.ZIJP,NUCLEAR DATA IN SCIENCE AND TECHN..IAEA.VIENNA.2(1973)271.99. O.GLOMSET,A.C.PAPPAS.INDC(NOR)-1/G.1972.P.3.
100. R.DOBROZEMSKY,F.PICHLMAYER,F.P.VIEHBOECK.SGAE-PH-104. 197KSEE ALSOREF.75 AND ALSO EANDC( OR)-68,1968.P.11).
101 . H.LIOU.F.RAHN.C.HO.J.RAINWATER,W.W.HAVENS,JR..TRANS AM.NUCL.SOC.,13(1970)300.
102. G.H.E.SIMS,D.G.JUHNKE, J.INORG.NUCL.CHEM.,32(1970)2839.103. S.F.MUGHABGHAB.R.E.CHRIEN.PHYS.REV.,174(1968)1400.104. J.W.ROGERS.J-J.SCOVILLE,NUCL.SCI.ENG.,33(1968)350.105. J.T.REYNOLDS.C.R.LUBITZ.I.ITKIN,D.R.HARRIS,KAPL-3327(ENDF-112),1967.106. R.H.FULMER.L.J.ESCH.F.FEINER,T.F.RUANE.WASH 68 E20.1968.107. M.DEMMELER.R.HECKER.H.IONAS,K.KLEINSCHNITTGER.D.V.S.RAMAKRISHNA.
ATOMWIRTSCHAFT,16(1971)532.108. H. JONAS,R.HECHER.W.GIESSER,ATOMKERNENERGIE.25(1975)271.109. M.D.RICABARRA.R.TURJANSKI,G.H.RICABARRA,CAN.J.PHYS.,47(1969)2031.110. G. E. STOKES,R.P.SCHUMAN,0.0.SIMPSON.NUCL.SCI.ENG.,33(1968)16(SEE ALSO
TRANS.AM.NUCL.SOC..6(1963)41).111. S.LATEK,J.TOPA.NUKLEONIKA,13(1968)881.112. L.LESAGE.R.SHER.REACTOR PHYSICS IN THE RESONANCE AND THERMAL REGIONS.
PROC.ANSMATH.TOP.MEET.SAN DIEGO,CALIF.,2(1966)175.113. R.P.SCHUMAN,J.R.BERRETH.IN-1296,1969.114. E.H.OTTEWITTE.J.M.OTTER.P.F.ROSE,C.L.DUNFORD.AI-AEC-12990.1971.115. ARGONNE NATIONAL LAB.,ANL-6580,1962,P.32.116. E.FAST.J.J.SCOVILLE.IDO-16781,1962,P.2.117. S.P.KAPCHIGASHEV.YU.P.POPOV.AT.ENERG.(USSR).15(1963)120.118. G.JOANOU,C.STEVENS,GA-5885,1964.119. P.W.DE LANGE.C.B.BIGHAM.NUCL.APPL.,4(1968)190.120. H. HEIMEL.M.HEINDLER,ATOMKERNENERGIE,20(1972)135.121. C.R.PIERCE.D.F.SHOOK,NUCL.SCI.ENG.,31(1968)431.122. CM. JACKS,DP-608.1961 .123. J.W.CONNOLLY,A.ROSE,T.WALL.AAEC/TM 191,1963.124. N.P.BAUMANN.DP-817,1963.125. M.BRESESTI.A.M.BRESESTI-DEL TURCO,A.ROTA,AERE-R-4500,PART 111,1964,
P.221.126. J.H.GILLETTE.ORNL-4013,1965.P.5.127. L.BELLER.D.LATHAM.J.OTTER.NORTH AMERICAN ARIATION.INC -,NAA-SR-12500,
1967.128. G.BORCHARDT.JUL-503-RX,1967.129. T.WALL,AAEC/TM466,1968.130. R.A.KARAM.T.F.PARKINS0N.66WASH,1966,P.171.131. R.SHER.L.LESAGE.T.J.CONNOLLY.H.L.BORWN,TRANS.AM.NUCL.SOC..9(1966)248.132. D.F.SHOOK,C.R.PIERCE.TRANS.AM,NUCL.SOC.,10(1967)261.133. H.L.BROWN.JR..T . J .CONNOLLY,W.K.FOELL.TRANS.AM.NUCL.SOC.,5(1962)375.134. H.L.BROWN.DISSERTATION ABSTRACTS SECTION B.27(1966)1244.135. G.J.KIROUAC.H.M.EILAND.PHYS.REV.C,11(1975)895.136. J.H.GILLETTE.ORNL-4155,1967.137. S.J.FRIESENHAHN.D.A.GIBBS.E.HADDAO.F.FROEHNER,W.M.LOPEZ.J.NUCL.
ENERGY,22(1968)191.138. C.R.PIERCE,D.F.SHOOK.D.BOGART.NASA-TN5628,1970.
PART 2-1 251
139. V.MARKOVIC.A.KOCIC.BULL.BORIS KINDRIC INST.NUCL.SCI.NUCL.ENG. .22(1971 ) 1 .
140. R.E.COTE BULL.AM PHYS.SOC.,6(1961)417.141 . C.R.PIERCE.NASA/0-4938.1968.142. R.SHER,PERSONAL COMMUNICATION CITED IN NEA/DATA BANK INTERNAL
FILE(SEE ALSO "KEY TO NOTES" NO.16).143. P.P.DAMLE.A.FABRY.R.JACQUEMIN,EANDC(E)-76.1967.P.107.144. G.WOLF.NUKLEONIK.2(1960)255.145. T.B.RYVES.K.J.ZIEBA,J.PHYS.A.7(1974)2318.146. J.I.KIM,F.ADAMS,RA0I0CHIM.ACTA.9(1968)61.147. W.KOEHLER,E.SCHNEIDER,NUKLEONIK,12(1969)197(SEE ALSO REF.148).148. E.SCHNEIDER.EANDC(E)89.1968.P.43.149. K.JIRLOW,E.JOHANSSON,J.NUCL.ENERGY,PART A.11(1960)101.150. R.A.BENNETT.NUCLEAR PHYSICS RESEARCH QUARTERLY REP..HW-63576 ,
1960,P.26.151. M.BROSE,DISSERTATION TECHNISCHE HOCHSCHULE KARLSRUHE,1960ISEE ALSO
NUKLEONIK,6(1964)134).152. G.BEN-DAVID.B.HUEBSCHMANN.J.NUCL.ENERGY.PARTS A/B,16(1962)291 .153. E.JOHANSSON,DISS.CHALMERS TEKN.HOGSKOLA.G0TE80RG.1966.154. R.L.SIMONS,W.N.MC ELROY,BNWL-1312(UC-34)1970.155. J.I.KIM.F.ADAMS,RADI0CHIM.ACTA.8(1967)165.156. D.BRUNE.K.JIRLOW,J.NUCL.ENERGY,17(1963)350.157. V.A.KONKS.F.L.SHAPIRO.SOV.PHYS..JETP,20(1965)531.158. J.HALPERIN.J.H.OLIVER,ORNL-3320,1962,P.2.159. M.J.CABELL.CAN.J.CHEM.,37(1959)1094.160. M.MONSECOUR.P.DE REGGE,J.INORG.NUCL.CHEM.,37(1975)1841.161 . R.W.ATTREE.M.J.CABELL,R.L.CUSHING.J.J.PIERONI.CAN.J.PHYS.,4 0( 1962)194162. R.E.COTE.H.DIAMOND,J.E.GINDLER,H.L.A.SHWE,PHYS.REV..176(1968)1421 .163. S.M.KALEBIN.P.N.PALEJ.P.N.IVANOV,Z.K.KARALOVA,G.M.KUKAVADZE .
Z.I.PYZH0VA,G.V.RUK0LAJNE.68DUBNA,ACC-61/18.1968,P.18(SEE ALSO ATOM-NAYA ENERGIYA.26(1969)507 AND SOVIET ATOMIC ENERGY,26(1969)588).
164. J.R.DEEN.E.LINN DRAPER,JR.,J.J.CHROMIK,TRANS.AM.NUCL.SOC..16(1973)316165. G.G.MYASISCHEVA.M.P.ANIKINA.L.L.GOLO'DIN.B.V.ERSHLER.AT.ENERG. (USSR) .
2(1957)22(TRANSL.IN SOVIET ATOMIC ENERGY,5(1957)230).166. F.J.JOHSTON,J.HALPERIN,R.W.STOUGHTON.H.NUCL.ENERGY,11(1960)95.167. L.I.TIREN.J.M.JENKINS,UK AEE REPORT AEEW-R.1962.P.163.168. J.B.SAMSON.GA-3069.1962.169. J.HARDY,NUCL.SCI.ENG..22(1965)121.170. M.BROSE,NUCL.SCI.ENG..19(1964)244.171. N.M.STEEN.WAPD-TM-971.1970.172. W.K.FOELL.T.J.CONNOLLY.NUCL.SCI.ENG.,21(1965)406.173 . M. ASGHAR . C. M. CHAFFEY , M. C . MOXON. N. J . PATTENDEN, E . R . RAE . C . A. UTTLEY . NUCL .
PHYS.76(1966)196.174. M.R.BHAT.R.E.CHRIEN,PHYS.REV.,155(1967)1362.175. R. R. SMI TH.T.O.PASSEL.S.D.REEDER.N. P. ALLEY, R.L. HEATH. IDO- 16226, 1955.176. H.DERRIEN.NEANDCtE )163U. 1975. P. 73.177. YU.YA.KONAKHOVICH.M.I.PEVZNER.AT.ENERG. (USSR) .8( 1960 )47( TRANSL . IN
SOVIET ATOMIC ENERGY.8(1961)39).178. M.J.CABELL.CAN. J.PHYS. .36( 1958)989.179. E.M.GRYNTAKIS,J.I.KIM.J.INORG.NUCL.CHEM.,36(1974)1447 (SEE ALSO
REF. 180).180. E.M.GRYNTAKIS,THESIS,TECHNICAL UNIVERSITY OF MUNICH,DM-6909, 1976
(SEE ALSO REF. 179).181 . F.B.SIMPSON. W.H.BURGOS, J.E.EVANS. H.W. KIRBY . NUCL .SC I. ENG. . 12( 1962)243.182. M. K . DRAKE . P . F . NICHOLS . GA-7462 ,1967.183. B.M.ALEKSANDROV.M. A . BAK . A . S . KR IVOKHATSK 11 ,E . A . SHLYAMIN . SOVIET ATOMIC
ENERGY,32(1972)203.184. T.A.EASTWOOD, R.W.WERNER, CAN. J.PHYS. ,38( 1960)75 1 .185. J.HALPERIN, R.E.DRUSCHEL.R.W.STOUGHTON, A. E.CAMERON, R.L. WALKER,
ORNL-3320.1962.P.2.186. J. C. CONNOR, R.T. BAYARD, D.MAC DONALD .S . B .GUNST ,NUCL .SCI .ENG. ,29( 1967)
408.187. F.B.SIMPSON,J.W.CODDING.JR.,NUCL.SCI.ENG.,28(1967)133.188. J.HALPERIN, C.R.BALDOCK, J.H.OLIVER. NUCL. SCI. ENG. .21 ( 1965)257 (SEE ALSO
REF.275).189. M. S. MOORE.L.G.MILLER.O.D.SIMPSON,PHYS.REV..118(1960)714.190. J.HALPERIN, F.J. JOHNSTON, R .W. STOUGHTON. J.H.OLIVER. E.L.BLEVINS.
R.E.DRUSCHEL,A.L.HARKNESS.B.A.SWARZ,NUCL.SCI.ENG. , 16( 1963)245.191. C.B.BIGHAM.AECL-1910,1964 (SEE ALSO CRRP-1 1 83 , 1964 ).192. L.J.ESCH.F.FEINER.TRANS.AM.NUCL.SOC. ,7( 1964)272.193. F.FE1NER.L.J.ESCH.66 SAN DIEGO,2(1966)299.194. T. YASUNO.NUCL.SC I .TECHN. ,2( 1965)532.195. N.L.SNIDOW.ADVANCED PRODUCTS ENG.DEPART..BAW-393-5.1966.196. D.E.CONWAY,S.B.GUNST.NUCL.SCI.ENG. ,29( 1967)1 .197. H.H.HENNIES.66PARIS 1 1 . I A E A , 1 9 6 7 , P . 3 3 3 .198. M.J.CABELL.66 PARIS I I . I A E A , 1 9 6 7 . P . 3 .199. J .HARDY.JR . ,NUCL .SC I .ENG. .27 (1967 )135 .200 . L.W.WESTON.R.GWIN.G.DE SAUSSURE . R. R.FULLWOOD.R.W. HOCKENBURY, NUCL. S C I .
ENG. .34 (1968)1 (SEE ALSO TRANS.AM.NUCL.SOC. .10(1967)220) .201 . M.G.CAO.E.MIGNECO, J . P. THEOBALD, M.MERLA, J . NUCL .ENERGY , 24( 1970) 1 1 1 ( SEE
ALSO NUCL.DATA FOR REACTORS,VOL . I . IAEA-CN-26 /19 .1970 .P .419 . ) .202 . M. A. BAK, K . A. PETRZHAK , YU . G. PETROV . YU. F . ROMANOV , E . A . SHLYAMIN, AT . ENERG .
(USSR) ,28(1970)359(TRANSL. IN SOVIET ATOMIC ENERGY,28(1970)460) .
252 GRYNTAKIS et al.
203. H.M.EILAND.L.S.ESCH.F.FEINER.J.L.MEWHERTER,NUCL.SCI.ENG. ,44( 1971 ) 180.204. A.OKAZAKI.M.LOUNSBURY,R.W.DURHAM,CHALK RIVER REP..AECL-2148. 1964 .205. E.CLAYTON,AECD-4167.1955.206. C.G.CAMPBELL,R.G.FREEMANTLE,M.J.POOLE.PROC.2ND INTERN.CONF.PEACEFUL
USES ATOMIC ENERGY.GENEVA.16(1958)233.207. R.W.STOUGHTON.J.HALPERIN.NUCL.SCI.ENG.,6(1959)100.208. J.HARDY.JR..D.KLEIN.G.G.SMITH.NUCL.SCI.ENG.,9(1961)341.209. G.H.HANNA.W.H.WALKER.EANDC(CAN)-20.1963.210. K.PARKER.AWRE-O-82/63.1963.2 1 1 . G .J0AN0U.GA-5944 ,1964 .2 1 2 . R.G.FREEMANTLE.REP.AEEW-M-502.1965.2 1 3 . HELLSTRAND.NUCKLEONIK,8(1966)1(SEE ALSO AKTIEBOLAGET ATOMENERGI
REPORTS.AE-181.1965) .2 1 4 . G.DE SAUSSURE.L.W.WESTON.R.GWIN.R.W. INGLE. J.H.TODD,NUCLEAR DATA FOR
REACTORS . ( PROC . CONF . PAR IS , 1966 ) . IAE A. 2 ( 1966 ) 233 .2 1 5 . A. J.DERUYTTER.C.WAGEMANS.68WASH. 1( 1968)475 .2 1 6 . UY.V.RYABOV.SO DON-SIK,N.CHIKOV.N.YANEVA.AT.ENERG.(USSR).24(1968)351
(TRANSL. IN SOVIET ATOMIC ENERGY,24(1968)435) .2 1 7 . E. M.P AGE .K.L.MAHNA. NEUTRON CROSS SECTIONS AND TECHNOLOGY , PROC .OF THE
3RD CONF.(CONF-710301) OF UNIV.OF TENNESSEE.KNOXVILLE.1971,P.469.2 1 8 . J.GADO.CENTRAL RESEARCH INSTITUT FOR PHYSICS.BUDAPEST.REP.KFKI-74-45.
1974 .2 1 9 . G.K.UNDERHILL,DISSERTATION ABSTRACTS SECTION 8 . 3 4 ( 1 9 7 4 ) 6 0 2 6 .2 2 0 . C.WAGEMANS.A.J.DERUYTTER.PERSONNAL COMMUNICATION CITED IN NEA DB
FILE (SEE "KEY TO NOTES".NR.16) . 1976 .2 2 1 . R.W.JONES,EAN(CAN)13/4 .1962.2 2 2 . I .H.CROCKER,EAN(CAN)17/4 ,1963.223 . R.W. DURHAM . G . C . HANNA. M. LOUNSBURY .C . B . BIGHAM , R . G . HART . R.W. JONES .
66PARIS I I , I A E A , 1 9 6 7 . P . 1 7 .2 2 4 . I .V.G0RDEEV.V.Y.PUPK0.PR0C.2ND INTERN.CONF.PEACEFUL USES OF ATOMIC
ENERGY.IAEA.GENEVA.16(1953)141.2 2 5 . E. J.HENNELLY,W.R.CORNMAN,N.P.BAUMANN,68WASH-1271 , 1968.2 2 6 . B.HINKELMANN.2ND INTERN.CONF.ON NUCLEAR DATA.HELSINKI ,CN-26 /15 .1970 .2 2 7 . V.E.PILCHER.D.J.HUGHES.J.A.HARVEY.BULL AM.PHYS.SOC. .1 (1956)187.228. S.PEARLSTEIN.CONFERENCE ON NEUTRON CROSS SECTION TECHNOLOGY.
CONF-660303,BOOK 1,P.251.WASHINGTON 22-24 MARCH 1966.229. J.HARVEY,R.SCHWARTZ,PROGRESS IN NUCL ENERGY,PHYS.AN0 MATH..VOL.2
(PERGAMON PRESS,LONDON.1958)P.51 .230. M. J.CABELL. T.A.EASTWOOD, P. J. CAMPION, J. NUCL. ENERGY, 7 ( 1958)81.231. J.HALPERIN,J.H.OLIVER,PROC.2ND INTERN.CONF.PEACEFUL USES ATOMIC
ENERGY.IAEA GENEVA.16(1958)64.232. J.R.BERRETH.R.P.SCHUMAN.WASH-1041 , 1962, P. 37.233. A. OKAZAKI.M.LOUNSBURY. R.W. DURHAM, I . H . CROCKER , AECL-1965, 1964.234 . N. P . BAUMANN. J . D. HALFORD. D. J . PELLARIN , NUCL . SCI. ENG. . 32 ( 1968) 265 .235. B.R.SEHGAL.TRANS.AM.NUCL.SOC..6( 1963)41 .236. A. D. CARLSON. S. J . FRIESENHAHN. W.M.LOPEZ, M.P. FRICKE. NUCL. PHYS. A, 141
(1970)577.237. H.L.ANDERSON.PHYS.REV.,80(1950)499.238. J.A.HARVEY.D. J.HUGHES, R.S. CARTER, V.E.PILCHER. PHYS. REV. ,99( 1955) 10.239 . R . L . MACKL IN. H. S . POMERANCE , J . NUCL . ENERGY , 2 ( 1956 ) 243 .240. L.M.BOLLINGER.R.E.COTE,D.A.DAHLBERG,G.E.THOMAS,PHYS.REV. , 105( 1957)661241. J.HARDY.JR.,G.G.SMITH,D.KLEIN.NUCL SCI.ENG..14(1962)358.242. J.W.WEBSTER.ORNL-TM-1448.1966.243 . S . H. EBERLE . H. J . BLEYL , H. BRAUN. A. V. BAECKMANN . L . KOCH, REPORT KFK-1453
(EUR-4726D). 1972.P. KSEE ALSO REF.280).244. J.D.SPENCER,N.P.BAUMANN.TRANS.AM.NUCL.SOC. 12( 1969)284.245. C.L.DUNFORD.H.ALTER.NAA-SR-12271 , 1967.246. H. IHLE. H. MICHAEL, A. NEUBERT, A. J. F.BLAIR. P. DAMLE .M. V. BODNARESCU . J .
INORG.NUCL.CHEM.,34(1972)2427.247 . L . P . ABAGYAN. A . G. DOVO JENKO . S . N. ZAKHAROVA. V . F . KAPUSTINA,M. N. NIKOL AEV .
D.V.PETROVA,PROC.2ND SOVIET CONF .,73KIEV,1(1973)246.248. J. P. BUTLER, M. LOUNSBURY, J.S.MERR IT. CAN. J. PHYS. ,35( 1957)147.249. F.B.SIMPSON.R.P.SCHUMAN.TRANS.AM.NUCL.SOC. ,6( 1963)43.2 5 0 . T. E. YOUNG. F . B. SIMPSON, J . R . BERRETH. M.S. COOPS. NUCL. S C I . ENG. . 3 0 ( 1 9 6 7 ) 3 5 52 5 1 . L.M.BOLLINGER.R.E.COTE,G.E.THOMAS,PROC 2ND INTERN.CONF . PEACEFUL USES
ATOMIC ENERGY (PROC. CONF. GENEVA. 1958) . 15( 1958 )127 .2 5 2 . P.J .PERSIANI .J .J .KAGANOVE.A.E.MC ARTY,T ID-18590 ,1963 .2 5 3 . M. J .CABELL, M.WILK INS, J . INORG.NUCL.CHEM. ,27 ( 1965)2481 .2 5 4 . J . J . S C H M I D T , K F K - 1 2 0 . 1 9 6 6 .2 5 5 . L.G.PONCELET.ARGONNE CODE CENTER ABSTRACT 249.WCAP-6073.1966.2 5 6 . R.M.HARBOUR.K.W.MAC MURDO,J.INORG.NUCL.CHEM..35(1973)1821 .2 5 7 . T .YASUNO.NUCL.SCI .TECHN. ,4 (1967)43.2 5 8 . G. C - HANNA. C. H. WESTCOTT . H. 0 . LEMMEL . B.R.LEONARD. JR. , J . S . STORY.
P.M.ATTREE.IAEA.ATOMIC.ENERGY R E V . , 7 ( 1 9 6 9 ) 3 .2 5 9 . A.PRINCE.68WASH,2(1968)951(SEE ALSO REF.272 ) .260 . J . I .KIM,R.BECK,E.M.GRYNTAKIS.R.ZAGHLOUL.NUCLEAR INSTRUMENTS AND
METHODS.165( 1 9 7 9 ) 5 6 5 .2 6 1 . F.W.CORNISH,M.LOUNSBURY.CRC-633.1956.262 . M .W.DYOS.NUCL.SCI .ENG. ,34 (1968)181 .263 . B.G.EROZOLYMSKY. I .E . KUTIKOV. Y . P . DOBRYNIN.M. I . PEVZNER ,L .S .DANELYAN ,
S.S.MOSKALEV,J.NUCL.ENERGY.4(1957)86 .264 . P.A.KRUPCHINSKY.J.NUCL.ENERGY.6(1957)155.2 6 5 . B .R .LEONARD,JR. ,E .J .SEPPI . W. J .FRIESEN,NUCL.SCI.ENG. , 5 ( 1 9 5 9 ) 3 2 .
PART 2-1 253
266. W. H. WALKER. C.H. WES TCOTT. T.K.ALEXANDER, CAN. J.PHYS. , 38 ( 1960)57.267. W.H.NICHOLS.NUCL.SCI.ENG. .17(1963)144(SEE ALSO 1RANS.AM.NUCL.SOC. .5
(1962 )374 ) .268. M.K.DRAKE,GA-6576.1965.269 . J . L . COOK , A. L . WALL . AAEC/TM362 . 1966 .270. C.WAGEMANS.A. J .DERUYTTER , NUCL . SCI .ENG . ,60( 1976)44(SEE ALSO 75WASH.GB
17,1975).271 . D. S. CRAIG,C.H.WESTCOTT.CAN.J.PHYS. ,42(1964)2384.272. A.PRINCE,TRANS.AM.NUCL.SOC..10(1967)228(SEE ALSO REF.259).273. R.W.BENJAMIN.V.D.VANOERVELDE.T.C.GORELL.F. J.MC CROSSON. 75WASH, 1975,
P.224.274. R.E . COTE, L.M. BOLL INGER.R.F. BARNES. H. DIAMOND . PROC . 2ND INTERN. CONF.
PEACEFUL USES ATOMIC ENERGY,IAEA.GENEVA,16(1958)77.275. J.HALPERIN. J.H.OLIVER.ORNL-2679. 1964.P. 13.276 . R . L . FOLGER, J . A. SMITH. L . C . BROWN . R . F . OVERMAN. H. P . HOLCOMB. 68WASH.2(1968)
1279.277 . T . E . YOUNG, S . D. REEDER , NUCL . SCI . ENG . . 40( 1970) 389 .278. B.C.RUSCHE. TRANS. AM. NUCL. SOC. , 14 ( 1971 )344 .279. R.P.SCHUMAN.WASH-1136.1969.PAGES 51 ,53 AND 53(SEE ALSO REF.113.
REF.288 AND I N - 1 3 1 7 , 1 9 6 9 ) .280. S.H.EBERLE.KFK-1544,1972,P.62(SEE ALSO REF.243) .2 8 1 . M. A. BAK. A. S . KRIVOKHATSK11 , K . A. PETR2HAK , YU . G . PETROV. YU . F . ROMANOV,
E. A.SHLYAMIN.AT.ENERG. (USSR) ,23( 1967 )3 16( TRANSL . IN SOVIET ATOMICENERGY,23(1967)1059).
282. R.M.HARBOUR,K.W.MAC MURDO.F.J.MC CROSSON.NUCL . SCI .ENG . . 50( 1973 )364 .283. J . J.SCOVILLE.E. FAST, WASH- 1053. 1964, P. 78 .284 . S . T . PERK INS . G. F . AUCHAMP AUGH. R . W. HOFF . C . D . BOWMAN. NUCL . SC I . ENG. . 32
( 1 9 6 8 ) 1 3 1 .285. 0 . D. S IMPSON, F . B. SIMPSON. J . A . HARVEY , G. G. SLAUGHTER. R. W. BENJAMIN,
C.E.AHLFELD,NUCL.SCI.ENG.,55(1974)273.286. C D . BOWMAN. G.F . AUCHAMP AUGH, S .C.FULTS .R.W.HOFF .PHYS.REV. , 166( 1968) 12 19287. R.C.KIIKALA.W.L.PURCELL, J . R .WORDEN, 66WASH, 1( 1966)75 .288. R.P.SCHUMAN.WASH-1124,1968.P.72(SEE ALSO REF.113,279 ) .289. M.C. THOMPSON. M.L.HYDER.R. J.REUL AND, J.I NORG . NUCL. CHEM. ,33( 1971 )1553.290. J . R . BERRETH.F.B.SIMPSON.B.C.RUSCHE.NUCL.SCI.ENG.,49(1972)145.291 . J.HALPERIN. R.E. RUSCHE, R.E.EBY.ORNL-4437. 1969. P. 20.292. C.H.WESTCOTT.W.H.WALKER,TK.ALEXANDER,2ND INT .CONF . PEACEFUL USES OF
ATOMIC ENERGY.IAEA,GENEVA.16(1958)70.293. J.HALPERIN. J.H.OLIVER,R.W.STR0UGHT0N.0RNL-4581 , 1970.P.37.294. R.W.BENJAMIN,K.M.MAC MUROO, J.D. SPENCER. NUCL . SCI .ENG . ,47( 1972>203<SEE
ALSO 3RD CONF.NEUTRON CROSS SECTION AND TECHN..KNOXVILLE.TENNESSEECONF-710301,2(1971)843).
295. CHETHAM-STRODE.ORNL-3832.1965.P. 1 .296. R. W.BENJAMIN. C.E.AHLFELD, BULL. AM. PHYS. SOC. . 19( 1974)599.297. J.HALPERIN. J.H.OLIVER,R.W.STOUGHTON.ORNL-4706. 1971 .298. C.E . BEMIS. JR. . J .W. T . DABBS .G. D . JAMES , N.W. HILL .M. S .MOORE . A . N .ELLIS .
0RNL-4976.1974.P.36.299. M.S.MOORE.J.H.MC NALLY,R.D.BAYBARZ.PHYS.REV.C,4(1971)273.300. K.W.MAC MURDO.R.M.HARBOUR. J. INORG.NUCL.CHEM. ,34( 1972)449.301 . K.D.ZHURAVLEV.N. I . KROSKIN . A . P . U JETV JER IKOV . AT . ENERG . (USSR) .39( 1975)
285.302. O.GRENECHE,NEANDC(E)163U,1975.P.43.3 03. B.GORDON.E.V.WE INSTOCK.WASH-1093. 1968.P.28.304. P.E.SPIVAK ET AL.,PROC.OF INTERN.CONF.ON PEACEFUL USES OF ATOMIC
ENERGY.GENEVA.5(1956)172.305. J. HALPERIN. C.E. BEMIS. R.E.DRUSCHEL.J.R. STOKELY.NUCL.SC I. ENG. .37( 1969)
228.3 06. J.A.SMITH.C.J. BAN ICK .R.L.FOLGER.H.P.H.P. HOLCOMB. I. B . RITCHE R . 68WASH. 2
(1968)1285.307. E.M.GRYNTAKIS. J. I .KIM, RADIOCHIMICA ACTA. 22( 1975) 128 .308. IAEA,TECHNICAL REPORTS SERIES NO.107.VIENNA.1970.309. N.P.BAUMANN, WASH-1046. P.49,1964.310. C.M.LEDERER,V.S.SHIRLEY.TABLE OF ISOTOPES .SEVEN EDITION 1978.
(ALSO 6TH ED.1967). WILEY-INTERSCIENCE PUBL..NEW YORK.311 . W.BLASER.A.WYTTENBACH.P.BAERTSCHI . J. I NORG. NUCL .CHEM. ,33( 1971 )1221 .312. R.VAN DER LINDEN,F.DE CORTE.P.VAN DEN WINKEL,J.HOSTER.J.RADIONAL.
CHEM. .11(1972)133.313. R.A.BENNETT.NUCLEAR PHYSICS RESEARCH OUATERLY REP..HW 68389(1961)50.314. R.DAHLBERG.K.JIRLOU.E.JOHANSSON,J.NUCL.ENERGY.14(1961)53.315. T.E.STEPHENS0N,BNL961(T-401).1965.316. G.H.SIMS. J.INORG.NUCL.CHEM. ,29( 1967)593.317. G.H.E.SIMS.D.G. JUHNKE, J. INORG. NUCL .CHEM. .31 ( 1969)3721 .318. N. T . KASHUKEEV. YU . P. POPOV, F . L . SHAPIRO. J . NUCL .ENERGY . PART . A/B.
14(1961)76.319. R.L.D.FRENCH,B.BRADLEY.NUCL.PHYS. ,65( 1965)225.320. W.K0HLER,H.SCHMELZ,NUKLE0NIK,9( 1967)270.321. L.L.ANDERSON.HEALTH PHYS . , 1 O( 1964 )315 .322. R.G.BARDES.R.K.LANGE.J.B.SAMPSON.L.J.TOOT,REPORT GA 3069.1962.323. K.W.GEIGER.L.VAN DER ZWAN.NUKEONIK . 1 0( 1967 )277 .324 . R.G.STIEGLITZ.R.W. HOCKENBURG, R. C . BLOCK . NUCL . PHYS . , A163 ( 1971 ) 592 .325. S.P.KAPCHIGASHEV.YU.P.POPOV.AT.ENERG. (USSR) . 16( 1964)256.326. W.E.LAMB.PHYS.REV.,55( 1939)190.327. T.B.RYVES.J.B.HUNT.I . W.GOODIER. J.NUCL.ENERGY.22(1968)465.
254 GRYNTAKIS et al.
328. J.J.SCOVILLE ET AL..WASH-1041.1962.P.37.329. J.R.BERRETH.R.P.SCHUMAN,REPORT IDO-16827.1962.P . 18.330. F.FEINER.REP.KAPL 2000-16.1961.331. E.J.AXTON.J.NUCL.ENERGY,17(1963)125.332. R.C.BARR ALL, W.N.MCELROY, IAEA , PROC . SYMP . VIENNA, 1965. P. 251 .333. P.LOUWRIER.A.ATEN.JR..J.NUCL.ENERGY.PARTS A/B.19(1965)267.334. R.O.BAROES,J.BROWN,M.DRAKE,J.SAMPSON, TRANS.AM.NUCL . SOC . .4 (1961)276 .335. T.NANJYO.J.NUCL.SCI.TECHN.,7(197 0)126.336. 0.0.M0X0N.AERE-PR/NP14.1968,P.12.337. F.FEINER.L.J.ESCH.REP.KAPL2000-12.1960.338. T.A.EASTWOOD,R.D.WERNER,CAN.J.PHYS..41(1963)1263.339. E.M.GRYNTAKIS,J.I.KIM,J.RADIOANAL.CHEMISTRY , 46 ( 1978)159.340. LESAGE,R.SHER,PROC.ANS NAT.TOP.MEET.SAN DIEGO.CALIF.,1966.P.4 .3 4 1 . C.H.HOGG.L.D.WEBER.E.C.YATES,IDO-16744.1962.342. I.A.KONDUROV.A. I .EGOROV.M.KAMINKEV.E .M.KOROTKIN. A.M. NIK I T IN , AT .ENERG.
(USSR).24(1968)533.343. J.S.STORY,REP.AEEW-M122,1961.344. C.H.HOGG.L.D.WEBER.IN-1024,1966.345. G.H.SIMS.D.G. JUHNKE . J . INORG. NUCL .CHEM. ,29( 1967)2853.346. S.PEARLSTEIN,R.F.MILLIGAN.NUCL.SCI.ENG.,26(1966)281 .347. J.F.EMERY.J.INORG.NUCL.CHEM.,27(1965)903.348. J.G.BRADLEY.W.H.JOHNSON,NUCL.SCI.ENG.,47(1972)151.349. W.SKOLNIK.N.C.FRANCIS,TRANS.AM.NUCL.SOC. ,2( 1959)121 .350. R.H.FULMER,D.P.STRIKOS.T.F.RUANE.NUCL.SCI.ENG..46(1971)314.351. R.NILSSON.NUCLEAR PHYSICS.29(1962)66.352. R.P.SCHUMAN.100-1676 0,1961,P.13.353. R.E.DRUSCHEL,J.HALPERIN,ORNL-4306,1968.P.2.354. E.HELLSTRAND,G.LUNDGREN.NUKLE0NIK,4(1962)323.355. H.SHWE.R.E.COTE.PHYS.REV..179(1969)1148.356. M.J.CABELL.J.INORG.NUCL.CHEM..21(1961) 1 .357. H.F.FEINER.TRANS.AM.NUCL.SOC.,2(1959)121.358. M.J.CABELL,J.NUCL.ENERGY,PARTA,12(1960)172.359. J.HALPERIN ET AL..ORNL-3832.1965.P.4.360. P.M.LANTZ.ORNL-3679,1964.P.10.361. R.D.WERNER.T.A.EASTWOOD,NUCL.SCI.ENG.,21( 1965)20.362. W.H.WALKER.L.A.COPLEY.CAN.J.PHYS.,44(1966)1985.363. V.MARKOVIC.A.KONIC.BULLETIN BORIS KIDRIC INST . NUCL . S C I . . NUCL .ENG. .
18 (1967 )11 .364. J.HALPERIN ET AL. .ORNL-3994,1966.P.2 .365. S.P.KAPCHIGASHEV.AT.ENERG.(USSR).19(1965)294.366. J.J.SCOVILLE.E.FAST,T.F.PARKINSON,REACTOR PHYS.CONST.CENTER NEWS
LETTER NO.10,1965.367. F.LUX.W.KOHLER.PROGRESS REPORT IN NUCLEAR DATA RESEARCH IN THE
EURATOM COMMUNITY,1964,EANDC(E)57"V",1965 . P. 28.368. A.M.BRESESTI .M.BRESESTI , H. NEUMANN. J . INORG, NUCL .CHEM. ,29( 1967)2477.369. H.H.KRAMER.W.H.WALL,NUCL.SCI.ENG.,22(1965)37337 0. V.MAXIA,E.ORVINI,M.A.ROLLIER.NUCL.SCI.ENG.,35( 1969)88.3 7 1 . F.DE CORTE. A. SPEECKE . J . HOSTE . J . RADIOANAL. CHEM. ,3( 1969)205.372. J.HALPERIN,R.E.DRUSCHEL,ORNL-3679,1964,P. 15.373. D.A.KLOPP.W.F.ZAGOTTA.TRANS.AM.NUCL.SOC.,5( 1962)337.374. K.H.BECKURTS .M. BROSE ,M. KNOCHE .G.GRUGER ,W. PON ITZ .H.SCHMIDT .NUCL .SCI .
ENG..17(1963)329.375. C.N.KLEBER,NUCLEONICS,20(1962)162.376. E.K.S0K0L0WSKI.R.BLADH.REP.AE-351,1969.377. A . P . JA IN, R.E.CHRIEN. J.A.MOORE. H. PALERSKY.NUCL.SC I . ENG. , 17( 1963)319.378. I.E.DAYTON,W.G.PETTUS.NUCLEONICS.15(1957)86.379. T. A. EASTWOOD. E .MATYAS.D. J .HNATOWICH , CAN. J . PHYS . ,41 ( 1963) 1519.380. H.D.LEMMEL.C.H.WESTCOTT,J.NUCL.ENERGY,21 ( 1967 ) 4 17 .3 8 1 . L.J.ESCH.F.FEINER, TRANS.AM.NUCL.SOC., 7 (1964)78 .382. R.G.HART.G.B.BIGHAM.F.C.MILLER,AECL-1503.1962.383. R.E.COTE ET AL..PHYS.REV.,159(1967)1050 .384. 8NL/NNDC.PRIVATE COMMUNICATION TO NEA/OATA BANK, USA,1971.385. J.C.CONNOR, WAPD-TM-837,1970.386. J.HALPERIN.C.E.BEMIS. JR. .R.E.DRUSCHEL,R.E.EBY.ORNL-4706.1971,P.47. •387. H. M. E ILAND, S. WE INS TEN. K.W. SEEMAN.NUC.SC I . ENG. ,54( 1974) 286 (SEE
ALSO REF.74) .388. A.F.FEDOROVA,J.I.PISANKO,G.M.NOVOSYELOV,REPORT KIYAI -76-6 .1976 .
INSTITUTE JADERNYKH ISSLEDOVANIJ,KIEV/USSR .389. M.FRICKE,A.CARLSON,GULF-RI-A-10739.197.390. C.E.BEMIS. JR. R.E.DRUSCHEL, J.HALPERIN, J.R.WALTON, NUC. SCI . ENG. .
4 7 ( 1 9 7 2 ) 3 7 1 .3 9 1 . W.BROWNE,B.L.BERMAN,PHYS.REV./C.8(1973)24 (SEE ALSO UCRL-74840.1973).392. A.F.FEDOROVA,J.I.PISANKO.G.M.NOVOSYELOV.REPORT K IYA I -76 -7 .1976 .
INSTITUTE JADERNYKH ISSLEDOVANIJ.KIEV/USSR.393. D.C.SANTRY,R.D.WERNER.CAN.J.PHYSICS.51(1973)2441.394 . G. F . AUCHAMPAUGH. J . HALPE RIN . P . L . MACLIN, W. M. HOWARD. PHYS . REV . / C .
12(1975)1126.395. G.J.KIR0UAC.H.M.EILAND.75WASH.2(1975)776.396. M.F.ELGART.H.F.FINSTON,R.RUNDBERG,E.T.WILL IAMS.NUC.SCI. ENG. ,
58(1975)291 (SEE ALSO 75WASH,2(1975)792).397 . R . E . SLOVACEK , D. S . CRAMER . E . B . BE AN . R . W. HOCKENBURY . J . R . VALENTINE .
R.C.BLOCK,NUC.SCI.ENG..62(1977)455 (SEE ALSO BULL.AM.PHYS.SOC..20(1975)581).
PART 2-1 255
398. L.SAGE,A.K.FURR,TRANS.AMER.NUCL.SOC..23(1976)501.399. G.GLEASON.RAOIOCHEMICAL AND RAOIOANAL.LETTERS,23( 1975)3 17 .400. W.GLEASON.PRIVATE COMMUNICATION TO NEA/DATA BANK.ORL.USA.1977.4 01 . C.E.BEMIS.JR.R.E.DRUSCHEI I.HALPERIN,R.D.BAYBARZ.ORNL-4581 , 1970, P. 43.4 02. C.E.BEMIS.JR.J.H.OLIVER,R.EBY.J.HALPERIN.NUCL.SCI.ENG.,63( 1977)4 13.4 03. J.B.GARG,J.RAINWATER.W.W.HAVENS. JR.NUCL.SCI.ENG..65(1978)76 (SEE
ALSO CR-1860.1964) .404. G.GLEASON.RAOIOCHEMICAL AND RADIOANAL.LETTERS.26( 1976)39.4 05. R.R.WINTERS,R.L.MACKLIN,J.HAL PER IN.PHYS.REV.C.18(1978)2 092.406. R.SHER.68WASH.1(1968)253.4 07. S.A.REYNONS.W.T.MULL INS,ORNL-4466.197 0,P.74.4 08. R.E.DRUSCHEL.J.HALPERIN.ORNL-3994,1966.P.6.409. ENDL : TABULAR AND GRAPHICAL PRESANTATION OF 175 NEUTRON-GROUP
CONSTANTS DERIVED FROM THE LLL EVALUATED-NUCLEAR DATA LIBRARY.E.E.PLECHATY.D.E.CULLEN,R.J.HOWE RTON,J.R.KIMLINGE R. REPORTUCRL-50400.VOL.16.REV.2. 1978.
410. P.LANTZ.C.BALDOCK.R.STOUGHTON.L.IDOM,ORNL-3994,1966,P.2.411. D.BIDIN0STI.H.FICKEL.R.T0MLINS0N.58GENEVA.15(1958)459.412. E.FEHR.E.HANSEN.KAPL-2000-12,I,1960.P.33 (SEE ALSO KAPL-2000,
1,I960.P.30).413. G.BREIT.E.WIGNER,J.PHYSICAL REVIEW 49(1936)519.414. R.W.STOUGTON.J.HALPERIN.R.E.DRUSCHEL.F.J.JOHNSTON,P.M.LANT2 .
J.H.OLIVER,G.W.PARKER.60VIENNA.1960.P.239.415. BIPAL : A DATA LIBRARY FOR COMPUTING THE BURNUP OF FISSIONABLE
ISOTOPES AND PRODUCTS OF THEIR DECAY, E.KRAZOVCOVA,J.HEP,V.VALENTA,REPORT ZJE-227(1978),NUCL.POWER CONSTRUCTION DIVISION,INFORMATION CENTRE.PIZEN.CZECHOSLOVAKIA.
416. R.A.KARAM.T.F.PARKINSON.M.F.PANCZYK,AD-402668,FLA.USA. 1963.417. M.J.CABELL.M.WILKINS,AERE-R-6384,1970.418. W.SKOLNIK.N.C.FRANCIS.TRANS .AMER.NUCL.SOC.,2(1959)135 .419. N.P.BAUMANN.D.J.PELLARIN.TRANS.AMER.NUCL.SOC..(1964)27.420. H.T.MAGUIRE JR.H.M.FISHER,R.C.BLOCK.INT.CONF. ON NEUTRON
PHYSICS AND NUCLEAR DATA FOR REACTORS AND OTHER APPLIEDPURPOSES. AERE HARWELL. 25-29 SEPT.1978,PAGE 472.
421. R.A.DEAL.R.P.SCHUMAN.WASH-1053,1964,P.76.422. R.P.SCHUMAN.IN-1126,MTR,USA.1967,P. 19.423. W.LYON.H.ROSS,ORNL-4196,1967,P.66.424. M.LUCAS.R.HAGEMANN,R.NAUDET.C.RENSON,C.CHEVALIER,
MEETING ON THE TECHN. COMMITTEE ON NATURAL FISSION REACTORS,PARIS 19-21 DEC.1977, 1(1979)431.
425. T.B.RYVES. NUCLEAR SCIENCE AND ENGINEERING, 72(1979)357.426. J.OLSEN, RISO-M-1516,1972.427. J.K.AALDIJK.H.M.M.KORSTJENS,W.L.ZIJP,RCN-176.1972.428. H.MICHAEL,A.NEUBERT.R.WAGNER,A.J.BLAIR,NEANDC(E)-172U , 176 , P . 43429. W. MAENHAUT.F.ADAMS.J.HOSTE. J.RADIOANAL.CHEMISTRY.16(1973)39.430. T.SEKINE.H.BABA, J . INORG.NUCL.CHEMISTRY,40(1978)1977.431 . A.KOCICV.MARKOVIC.BULL. INST.BORIS KIDRIC.VOL. 18.NUC.ENG. . 19( 1968)13.432 . V . HAYODOM, W. BOONKONG, S . MAHAPANY AWONG , C . CHAIMONKON . BANGKOK , THAILAND .
THAI-AEC-23 PROGRESS REPORT,1969.433 . E.ABUL-ELA,I.HAMOUDA.AREAEE-165,CAIRO.UAR.1973.434 . V.D.GAVRILOV, V. A.GONCHAROV. V. V. IVANENKO. V.P . SMIRNOV . V . N . KUSTOV ,
75KIEV,6(1975)71.435. V.A.ANUFRIEV.T.S.BELANOVA.YU.S.ZAMJATNIN.A.G.KOLESOV.S.N.NIKOLSKIJ.
V. A. PORUCHIKOV. S . M. KALEBIN. V . S . ARTAMONOV, R. N. IVANOV. 76L0WELL ,2(1976).1252.
436. V.A.ANUFRIEV.A.G.KOLESOV.S.I . ,BABICH,V.A.SAFONOV,PROCEEDING OFTHE INTERN. CONF. ON NUCLEAR CROSS SECTIONS FOR TECHNOLOGY.KNOXVILLE 22-26 OCT. 1979. PAGE 877.
437 . V. A. ANUFRIEV .S.I. BABICH. V. N. NEFEDOV, V. A. PORUCHIKOV. V . S . ARTOMONOV ,R.N.IVANOF.S.M.KALEBIN, PROCEEDING OF THE INTERN.CONF. ON NUCLEAR CROSS SECTIONS FOR TECHNOLOGY. KNOXVILLE 22-26OCT. 1979, PAGE 907.
438. S.I.BABICH.N.G. KOCHE RYGIN, A. G. KOLESOV, V. A. PORUCHIKOV. V. A. SAFONOV.V.N.NEFEDOV.V.S.ATTOMONOV.T.S.BELANOVA.R.N.IVANOV,S.M.KALEBIN,PROCEEDING OF THE INTERN. CONF. ON NUCLEAR CROSS SECTIONS FORTECHNOLOGY, KNOXVILLE 22-26 OCT. 1979, PAGE 908.
439. K.D.ZHURAVLEV.N.I.KROSHKIN. SOVIET ATOMIC ENERGY 47(1979)565.440. M.KUROSAWA.K.SHIMIZU.J.ATOMIC ENERGY SOC.JAPAN.21(1979)505.441 . V.D.GAVRILOV, V. A.GONCHAROV, ATOMN AY A ENERGIYA(USSR ) ,44( 1978)246.
(SEE ALSO REPORT JADERNO-FIZICHESKIE ISSLEDOVANIJA,YFI-25( 1979)49 ).442. V.A.ANUFRIJEV,A.G.KOLESOV,V.N.NEFJODOV,R.N.IVANOV,S.I.BAB ICH,
A.P.CHE TVERIKOV.V.A.PORUCHIKOV,V.A.SAFONOV,V.S.ARTAMONOV,S . M.KALEBIN.ATOMNAYA ENERGIYA(USSR),46(1979)158 (SEE ALSO REPORT JADERNYEKOSTANTY.OBNINSK(USSR),YK-1.32.1979,P.24).
443. V.A.ANUFRIJEV,A.G.KOLESOV.S.N.NIKOL'SKIJ,V.A.SAFONOV.ATOMNAYAENERGIYA(USSR),47(1979)269.
444. V.A.ANUF RIJEV.S.I.BABICH,A.G.KOLESOV.V.N.NEFJODOV,V.S.ARTAMONOV.R.N.IVANOV,S.M.KALEBIN.REPORT JADERNYE KONSTANTY.OBNINSK(USSR).YK-1,32,1979,P.19.
445. U.N.SINGH.R.C.BLOCK.Y.NAKAGOME, NUCL.SCIENCE ENGINEERING.67( 1980)54.446. N.E.HOLDEN.REPORT BNL-NCS-51388,1981.
256 GRYNTAKIS et al.
447. "EVALUATED NUCLEAR STRUCTURE DATA FILE" (ENSDF) EDITED ANDMAINTAINED BY THE U.S NATIONAL NUCLEAR DATA CENTRE, BROOKHAVENNATIONAL LABORATORY, ON BEHALF OF THE INTERNATIONAL NETWORK FORNUCLEAR STRUCTURE DATA EVALUATION (JUNE 1984).
448. L.N.JUROVA. A.A.POLJAKOV, V.P.RUKHLO. JU.E.TITARENKO.S.F.KOMIN, O.V.SHVEDOV, B.F.MJASOEDOV. A.V.DAVYDOV,S.S.TRAVNIKOV, REPORT JADERNYE KONSTANTY, OBNINSK (USSR).ISSUE 1(55) (1984) P.3.
Annex
EFFECTIVE RESONANCE ENERGY VALUES
F. De CorteRijksuniversiteit Gent, Gent, Belgium
Many significant discrepancies in resonance integral data can be explainedby the fact that the epithermal neutron flux distribution is not proportional to1/E, but rather to l/E1+a, where a is a positive or negative constant close to zerowhich can be determined for the irradiation facility used. The correspondingcorrection to the infinite dilute resonance integral requires a tabulation of'effective resonance energy' values, which is given here.
The concept of the effective resonance energy (Er) - first developed byRyves [ 1 ] and later introduced in the field of (n,7) activation analysis byMoens et al. [2] and Jovanovic et al. [3] - is associated strictly with the assum-ption of a 1 /E1+<* epithermal neutron flux distribution, where a is consideredto be independent of neutron energy. For nuclides which obey the a(v) ~ 1/vlaw up to 1-2 eV, it can be shown that it is possible to calculate, with acceptableaccuracy, an a-independent Er value (in eV) [2, 3]:
with
PART 2-1 257
Here Er i is the energy of the ith resonance (in eV);gj is the statistical weight factor;Fn j is the neutron width;F j is the radiative width;Fj is the total width of resonance.
Er thus calculated is a useful parameter for the description of the epicadmiumreaction rate in a l /E1 + a epithermal neutron flux distribution:
/ECd
(EineV)
with 0e equal to the conventional epithermal flux
I o - 0.429 q0 0-429 q0
+(E r)a (2a+l ) (0 .55) a
where aQ is the 2200 m/s (n/y) activation cross-section and Io is the usuallytabulated (n,7) activation resonance integral integrated from the effective Cdcut-off energy (= 0.55 eV), and with the 1/v tail included, valid for an ideal 1/Eepithermal neutron flux distribution
/ _ r a(E)dE\
In the analysis outlined above, Er is an indispensable parameter in the conversionof experimentally determined I0(a) values to Io (which can be tabulated) and theconversion of tabulated Io values to practically useful Io (a) values. Thus, Io
tabulations should be accompanied by Ef values. It should be noted that simplemethods have been described for experimental a determination that are suitablein ordinary radioanalytical laboratories [4, 5]. Finally, the above-mentionedassumptions and approximations were shown to yield fairly satisfactory resultsin the practice of (n,7) activation analysis [5-7].
Table A-I lists calculated Er values for the (n,7) reaction on 128 targetisotopes which are of interest in (11,7) activation analysis [8]. Calculation isbased mainly on resonance parameter data from Brookhaven National Laboratory,Upton, New York [10, 11].
258 GRYNTAKIS et al.
TABLE A-I. CALCULATED Ef VALUES FOR THE (n, 7) REACTION ON128 TARGET ISOTOPES
Targetisotope
18O
"F23Na
26Mg
"Al
MSi
3.p
3 6 S
37C1
«Ar
*'K
46Ca
48Ca
4$Sc
50Ti5 'V
5 o a
s5Mn
58Fe
59Co
*Ni
w Cu65CuMZn
^ Z n
69Ga71Ga
"Ge
76Ge
75As
74Se
76Se
78Se
(eV)
1 140 000 + 80 000
44 700 ± 2200
3380 ± 3 7 0
257 000 + 33 000
11 800 ± 7 0 0
2280 ± 10
38 500 ± 6900a
13 700+ 1900
31000± 5600
2960 + 210a
1 330 000 ± b
5130 + 870
63 200 + 2500
7230 ±290
7530 ±830
468 ±51
637± 153
136 ± 7
14200± 1700
1040 ± 5 0
766± 130
2560± 260
590 ± 60
201 + 16
154 ± 18
3540 ±280
583 ±23
106 + 36
29.4 ± 1.2
577 ± 4 6
501 ± 35
Targetisotope
^Se
82Se
' 'Br
81Br
85Rb87Rb
MSr86Sr
89y
wZr96Zr
" N b
98Mo
10oMoM Ru
'0 2Ru
!04Ru
103Rh
106pd
108pd
110Pd
107Ag109Ag, 0 8 C d
"°Cd
" 4 Cd
" 6 Cd
u 3 In
" s In
" 2 Sn
" 6 Sn
122Sn
124Sn
(eV)
2940 ± 4 1 0
8540 ± b
69.3 ± 6.2
152 ± 14
839 ± 5 0
364 ± 11
469 ±33
795 ± 16
4300 + 340
6260 ± 2 5 0
338 ±7
574 ±46
241 ±48
672 ± 94
776± 124C
18! ± 7
495 ±50
1.45 ±0.01
282 ±6
39.7 + 2.0
950 ±86
38.5 ± 1.9
6.08 ± 0.06
243 ± 24
125 ± 16
207 ±39
726 ± 87
6.41 ±0.96
1.56 ±0.03
1.07 + 3
128 ±4
424 ± 59
74.2 ± 5.2
PART 2-1 259
Targetisotope
121Sbn 3 S b!20Te
123TeI24Te
126TeIJ8Te
l30Te, 2 7 ,
.33 C s
1 3 0Ba
l 3 2 Ba
134Ba
136Ba
138Ba
13»La
1 3 8Ce
1 4 0Ce
1 4 2Ce
141pr
1 4 6Nd
1 4 8Nd
1 5 0 Nd
l s 2 S m
154Sm153Eu158Gd
'«Gd
15»Tb
• « D y
' " H o
' " E r
170Er
(eV)
13.1 ±0.5
28.2 ± 1.7a
92.3 ±3.7
1210+ 100
285 ± 20
738 ± 52
2950 ±210
57.6 ± 2.3
9.27 ± 1.02
69.9 ±3.5
143 ± b
115 ±6
545 ± 38
15 700 ±500
76.0 ±3.0a
7200± 1300
1540± 1850
296 ± 12
874 ± 52
236+ 14
173 ± 21
8.53 ± 0.09
142 ± 10
5.80 ±0.23
48.2 ± 3.9
480 ± 34
18.1 ±0.9
224 ± 11
12.3 ±0.4
59.3 ±4.2
129 + 3
Targetisotope
169Tm
i68Y b
' " Y bW6Y f e
1 7 5 I .u
1 7 4 Hf
1 7 7 Hf
1 7 8 Hf
1 7 9 H f
1 8 0 Hf
181Ta
1S2W
18*W
1 8 5 R e
1 8 7 R e
1 8 9 O s
1 9 0 O S
1 M O s
" 3 I r
!90pt
.96p t
" 8 p t
" 7 A u
' " H g
" 8 H g
202Hg
2 M H g
2 O 3T1
2OST1
206pb
2 O 8 p b
J09Bi232Th
"8u
Er(eV)
4.80 ±0.10
0.61 ±0.01
602 ±48
412 ±21
16.1 ±0.8
29.6 ± 2.1
2.08 ± b
8.01 ±0.16
16.2 ± 1.9
115 ± 7
10.4 ±0.6
9.20 ±0.55
20.5 ±0.2
3.40 ±0.14
41.1 ± 1.6
12.3 ±0.4
114 + 2
89.7 ±3.6
2.21 ±0.20
27.6 ±0.6
291 ±4 4
106 ± 3
5.65 +0.40
93.5 ±0.1
39.3 ± 2.8
1960± 160a
276 ± 28
2960 ± 360
10 500 ± 1200
145 000 ±4000
1210 ± 60
54.4 + 0.5
16.9 + 0.2
No resonance data available.No error assignment possible.Experimental value (see Ref. [9]).
260 GRYNTAKIS et al.
REFERENCES TO THE ANNEX
[1] RYVES, T.B., MetrologiaS (1969) 119.[2] MOENS, L., DE CORTE, F., SIMONITS, A., DE WISPELAERE, A., HOSTE, J.,
J. Radioanal. Chem. 52 (1979) 379.[3] JOVANOVIC, S., DE CORTE, F., MOENS, L., SIMONITS, A., HOSTE, J., J. Radioanal.
Nucl. Chem. Articles 82/2 (1984) 379.[4] DE CORTE, F., et al., J. Radioanal. Chem. 62 (1981) 209.[5] DE CORTE, F., JOVANOVIC, S., SIMONITS, A., MOENS, L., HOSTE, J., in Use and
Developments of Low and Medium Flux Research Reactors (Proc. Int. Symp. Cambridge,MA, 1983), Supplement to Atomkernenerg. Kerntech. 44 (1984) 641.
[6] DE CORTE, F., et al., J. Radioanal. Chem. 72 (1982) 275.[7] MOENS, L., et al., J. Radioanal. Nucl. Chem. Articles 82/2 (1984) 385.[8] JOVANOVIC, S., Ph. D. thesis, Rijksuniversiteit Gent, 1984.[9] SIMONITS, A., JOVANOVIC, S., DE CORTE, F., MOENS, L., HOSTE, J., J. Radioanal.
Nucl. Chem. Articles 82/1 (1984) 169.[10] MUGHABGHAB, S.F., DIVADEENAM, M., HOLDEN, N.E., Neutron Cross Sections:
Neutron Resonance Parameters and Thermal Cross Sections. Part A:Z = 1-60, Vol. 1,Academic Press, New York (1981).
[11] MUGHABGHAB, S.F., Neutron Cross Sections: Neutron Resonance Parameters andThermal Cross Sections. Part B:Z = 61-100, Vol. 1, Academic Press, New York (1984).
2-2. DATA FOR 14 MeVNEUTRON ACTIVATION ANALYSIS
Z. BODY, J. CSIKAIInstitute of Experimental Physics,Kossuth University,Debrecen, Hungary
Abstract
DATA FOR 14 MeV NEUTRON ACTIVATION ANALYSIS.Suggested reactions for analysis are presented, together with their characteristic data,
for almost all natural elements. In addition, 337 recommended cross-sections at 14.5 MeVare also given for the (n, 2n), (n, p) and (n, a) reactions.
1. INTRODUCTION
One can advantageously use low-voltage neutron generators [ 1 ] as fast (andoccasionally thermal) neutron sources in neutron activation analysis. The energyof neutrons produced in the 3H(d,n)4He reaction depends on Ed, the bombardingdeuteron energy, and on the emission angle. The neutron energy and the relativeyield, as functions of the angle at Ed = 175 keV (commonly used with low-voltage accelerators) are given in Table I for thick targets. The effective cross-section values for the 27Al(n, a) standard reaction are also given there.
TABLE I. NEUTRON ENERGY AND RELATIVE YIELD VERSUS THEANGLE AT Ed = 175 keV FOR A THICK TARGET3
Angle
0
30
60
90
120
150
180
Average neutron"energy (MeV)
14.774(0.17)
14.678(0.15)
14.417(0.12)
14.069(0.08)
13.730(0.10)
13.487(0.12)
13.400(0.13)
Relative intensity
1.049
1.043
1.025
1.000
0.976
0.958
0.951
<Jeff (mb) forAl-27(n, a)
112.3
113.1
116.0
121.9
124.0
125.1
127.2
The cross-sections are taken from Refs [2,3],
261
262 BODY and CSIKAI
Although comparison with a standard is preferred for absolute measurementsin neutron activation analysis, knowledge of nuclear data — and of cross-sections,in particular — is important in order to choose the most favourable reaction orto estimate the expected activity and the role of interfering reactions. Taking intoaccount nuclear data only, the most effective identifying reaction is given foreach element in Table II.
2. THE ACTIVATION PROCESS
Let N be the number of radioactive nuclei, a the cross-section of the reaction,4> the neutron flux, n the number of target nuclei and X the decay constant of theradionuclides formed. The following differential equation can then be described:
(1)dt
where the first term on the right-hand side gives the increase in N because of theactivation process, while the second term gives the decrease owing to decay.
The general solution of this first-order linear inhomogeneous differentialequation is
N(t) = e" C + an /$(t)e+Xtdt (2)
where C is a constant of integration. Restricting the solution to a constant flux$ = 4>0 and assuming the initial condition N = 0 for t = 0 yields
N(t) = -J— (l-e-Xt) (3)A.
from which the activity at time t (i.e. the number of decays per unit time) will be
= <f>oan(l -e"Xt) (4)
The specific activity, i.e. the activity per unit target mass (m) - in disintegrationsper second per gram ((dis/s)/g) - will then be given as
A(t) , aa*0 -= 6.02 XI(T6 ^ l - e " " ) (5)
m M
PART 2-2 263
where a is given in mb, the atomic weight of element M is in grams and the targetisotopic abundance a is in per cent.1 This specific activity has been calculated fordifferent reactions assuming a flux of $0 = 109 neutrons-cm"2 s"\ as well asirradiation times of t = 10 min and t = 1 h, respectively (columns 9 and 10 ofTable II. The saturation values are also given in column 11 under the heading't = °°')- It should be noted here that this neutron flux value is a realistic onefor fast neutrons if they are produced by a neutron generator of average intensity,while for thermal neutrons (produced by the same generator) this value is too high,the overestimation being about two orders of magnitude.
Another consideration also has relevance if the final nucleus has more than asingle final state and if the ground state activity is used for analysis. In such a case,instead of Eq. (1), as many differential equations would have to be solvedsimultaneously as the number of the final states. For example, for two stateswe have
dt
and
dNc
d N mm =<Da m n-X r a N m (6a)
(6b)
where m and g indicate metastable and ground state quantities, respectively, andP is the ratio of the internal transition (IT) events (leading from the metastableto the ground state) to all decay events of the metastable state. All other quantitiesare the same as before.
Assuming again a constant flux <f> = $ 0 a nd initial condition Nm = Ng = 0
for t = 0, the solution of Eq. (6) will be
$ oamn l ( - e m t)Nm(t) = - 2 J 5 ^ (7a)
K
and
Ng(t) = *onxg xg xm
(7b)
1 1 disintegration per second s 1.00 X 10° Bq (becquerel).
Explanations of Tables II-Vare given on pp. 300 and 301.
TABLE II.
Atomic No./Element
5-B
7-N
8-O
9-F
10-Ne
11-Na
12-Mg
13-A1
14-Si
15-P
16-S
RECOMMENDED
Atomicweightofelement
10.811
14.0067
15.9994
18.9984
20.183
22.9898
24.312
26.9815
28.086
30.9738
32.064
REACTIONS
Targetisotopicabundance(%)
80.2
99.63
99.76
100
90.51
100
78.99
100
92.23
100
4.21
FOR ACTIVATION
Reaction
B-ll(n,p)Be-ll
N-14(n,2n)N-13
O-16(n,p)N-16
F-19(n,2n)F-18
F-19(n,p)O-19
Ne-20(n,p)F-20
Na-23(n,tt)F-20
Na-23(n,p)Ne-23
Mg-24(n,p)Na-24
Al-27(n,p)Mg-27
Al-27(n,a)Na-24
Si-28(n,p)Al-28
P-31(n,a)Al-28
S-34(n,a)Si-31
ANALYSIS WITH
Cross-section(mb)
3.3(0.6)
7.1(0.6)
35(4)
55(4)
19(2)
92
150(15)
35(4)
181(8)
75(4)
116(0.7)
226(30)
118(15)
138(35)
SMALL NEUTRON GENERATORS
Half-life
13.81(8) s
9.963(9) min
7.13(4)s
109.72(6) min
26.76(8) s
10.996(20) s
10.996(20) s
37.6(1)s
14.959(7) h
9.462(12) min
a 14.959(7) h
2.2405(3) min
2.2405(3) min
2.62(l)h
Gammaenergy(keV)
2124.8(7)
Annihilation
2741.2(5)6129.2(1)
Annihilation
197.1(1)1356.8(1)
1633.7(1)
1633.7(1)
439.9(2)
1368.5(1)2754.9(1)
843.7(1)1014.43(1)
1368.5(1)2754.9(1)
1779.0(1)
1779.0(1)
1266.1(1)
264
wo
Sa.oin
>
Atomic No./Element
Gammasperdecay
(dis/s)/g(t = 10 min)
(dis/s)/g(t= 1 h)
1.47
2.99
1.31
5.50
6.02
2.48
3.93
9.17
1.60
1.65
1.17
4.47
2.29
?..S4
X
X
X
X
X
X
X
X
X
X
X
X
X
X
10s
10s
106
10s
10s
106
106
10s
105
105
105
106
106
in4
(dis/s)/g((=oo)
Interfering reactions
5-B
7-N
8-0
9-F
10-Ne
11 -Na
12-Mg
13-A)
14-Si
15-P
16-S
33.0
200.
0.7668.8
194.
95.950.4
100.
100.
33.0
100.99.9
71.828.2
100.99.9
100.
100.
0.07
1.47 X 10s
1.52 X 10s
1.31 X 106
1.07 X 10s
6.02 X 10s
2.48 X 106
3.93 X 106
9.17 X 10s
2.72 X 10"
8.69 X 10s
1.99 X 10"
4.27 X 106
2.19X 106
4.71 X 103
1.47 X 10s
3.04 X 10s
1.31 X 106
1.74 X 106
6.02 X 10s
2.48 X 106
3.93 X 106
9.17 X 10s
3.54 X 106
1.67 X 106
2.59 X 106
4.47 X 106
2.29 X JO6
1.09 X 105
N-15(n,7); F-19(n,a); 0-17(n,d)
O-18(n,7)
F-19(n,7); Na-23(n,a); Ne-21(n,d)
F-19(n,7); Ne-20(n,p); Ne-21(n,d)
Ne-22(n,7)
Na-23(n,7); Al-27(n,a); Mg-25(n,d)
Mg-26(n,7); Si-30(n,«)
Na-23(n,7); Mg-24(n,p); Mg-25(n,d)
Al-27(n,7); P-31(n,a); Si-29(n,d)
Al-27(n,7); Si-28(n,p); Si-29(n,d)
Si-30(n,7); P-3l(n,p)
5
TABLE II (cont.)
Atomic No./
Element
17-C1
18-Ar
19-K
20-Ca
21-Sc
22-Ti
23-V
24-Cr
25-Mn
Atomicweightofelement
35.453
39.948
39.102
40.08
44.956
47.90
50.942
51.996
54.9380
55.847
Targetisotopicabundance
24.23
99.60
6.73
2.09
100
73.7
99.75
83.79
100
91.8
Reaction
Cl-37(n,p)S-37
Ar-40(n,p)CI-40
Ar-40(n,a)S-37
K-41(n,p)Ar-41
K-41(n,a)Cl-38
Ca-44(n,p)K-44
Sc-45(n,2n)Sc-44g
Ti-48(n,p)Sc-48
V-5 1(n,p)Ti-51
Cr-52(n,p)V-52
Mn-55(n,a)V-52
Mn-55(n,7)Mn-56
l ;e-56(n,p)Mn-56
Cross-section(mb)
28(3)
16(2)
10.0(1.5)
51(8)
33.5(2)
39(4)
188(14)
66(6)
33(3)
102(20)
32(5)
13 300(200)
98(7)
Half-life
4.99(2) min
1.32(2) min
4.99(2) min
1.827(7) h
37.24(5) min
22.15(2) min
3.927(8) h
43.67(9)h
5.752(7) min
3.760(8) min
3.760(8) min
2.5785(6) h
2.5785(6) h
Gammaenergy(keV)
3103.3(2)
1460.8(1)2840.2(3)
3103.3(2)
1293.7(1)
1642.4(1)2167.6(1)
1157.0(1)2150.8(1)
1157.0(1)
983.5(1)1312.1(1)
320.1(1)
1434.1(1)
1434.1(1)
846.8(1)1810.7(1)
846.8(1)1810.7(1)
toO NO N
WO:O
So
Atomic No./Element
17-C1
18-Ar
19-K
20-Ca
21-Sc
22-Ti
23-V
24-Cr
25-Mn
26-Fe
Gammasperdecay
(%)
94.1
77.529.9
94.1
99.1
31.642.4
58.222.8
99.9
100.100.
93.0
100.
100.
98.927.2
98.927.2
(dis/s)/g(t = 10 min)
8.65 X 10"
2.39 X 105
1.13 X 10s
3.24 X 103
5.90 X 103
3.30 X 103
7.30 X 10"
1.62 X 103
2.73 X 105
8.34 X 105
2.95 X 105
6.39 X 106
4.25 X I04
(dis/s)/g( t = 1 h)
1.15 X 105
2.40 X 10s
1.50 X 105
1.67 X 10"
2.34 X 104
1.04 X 104
4.08 X 105
9.63 X 103
3.89 X I0 5
9.89 X 105
3.51 X 10s
3.44 X 107
2.29 X 10s
(dis/s)/g(t=oo)
1.15 X 10s
2.40 X 10s
1.50 X 105
5.30 X 104
3.47 X 104
1.22 X 104
2.51 X 106
6.12 X 105
3.89 X I05
9.89 X 10s
3.51 X 10s
1.46 X 108
9.71 X 10s
Interfering reactions
S-36(n,7); Ar-40(n,a)
S-36(n,7); Cl-37(n,p)
Ar-40(n,7); Ca-44(n,a)
Cl-37(n,7); Ar-38(n,p)
V-51(n,a); Ti-49(n,d)
Ti-50(n,7); Cr-54(n,a)
V-5 l(n,7); Mn-55(n,a); Cr-53(n,d)
V-51(n,7); Cr-52(n,p); Cr-53(n,d)
Fe-56(n,p); Co-S9(n,a); Fe-57(n,d)
Mn-55(n,7); Co-59(n,a); Fe-57(n, d)
JOH
to
TABLE II (cont.)00
Atomic No./Element
27-Co
28-Ni
29-Cu
30-Zn
31-Ga
32-Ge
33-As
34-Se
35-Br
36-Kr
Atomicweightofelement
58.9332
58.71
63.54
65.37
69.73
72.59
74.9216
78.96
79.909
83.80
Targetisotopicabundance
100
26.1
68.3
69.2
30.8
48.6
60.1
7.8
100
9.0
50.69
17.3
Reaction
Co-59(n,7)Co-60m
Co-59(n,a)Mn-56
Co-59(n,2n)Co-58m+g
Ni-60(n,p)Co-60m
Ni-58(n,2n)Ni-57
Cu-63(n,2n)Cu-62
Cu-65(n,p)Ni-65
Cu-65(n,2n)Cu-64
Zn-64(n,2n)Zn-63
Ga-69(n,2n)Ga-68
Ge-76(n,2n)Ge-75m+g
As-75(n,2n)As-74
As-75(n,p)Ge-75m+g
Se-82(n,2n)Se-81m
Br-79(n,2n)Br-79m
Kr-86(n,2n)Kr-85m
Cross-section(mb)
18 800(1500)
29(2)
720(50)
95(10)
30(3)
551(11)
25(5)
931.8(13.l)b
178(27)
945(50)
1148(120)
1061(100)
19.2(2.0)
1008(120)
974(50)
350(35)
Half-life
10.47(2) min
2.5785(6) h
70.78(10) d
10.47(2) min
36.16(1 1) h
9.74(2) min
2.520(2) h
12.701(2)h
38.1(l)min
68.1(2) min
82.80(4) min
17.78(5) d
82.80(4) min
57.28(5) min
6.46(4) min
4.480(8) h
Gammaenergy(keV)
58.6(1)
846.8(1)1810.7(1)
810.8(1)
58.6(1)
1377.6(1)
Annihilation
1481.8(1)
Annihilation1345.8(1)
669.6(1)
1077.4(1)
264.6(1)
595.8(1)
264.6(1)
103.1(1)
613.7(1)
151.2(1)
wuD»aoV.
\
Atomic No./Element
27-Co
28-Ni
29-Cu
30-Zn
31-Ga
32-Ge
33-As
34-Se
35-Br
36-Kr
Gammasperdecay
2.02
98.927.2
99.4
2.02
77.9
196.
23.5
35.80.48
8.40
2.93
11.3
60.3
11.3
9.79
13.6
75.0
(dis/s)/g(t = 10 min)
9.31 X 107
1.30 X 10"
5.00 X 102
1.23 X 105
6.69 X 102
1.84 X 106
3.27 X 103
2.46 X 104
1.32 X 10s
4.75 X 10s
5.94 X 104
2.33 X 103
1.24 X 104
7.89 X 104
2.45 X 106
1.1 1 X 104
(dis/s)/g
(t = 1 h)
1.89 X 108
6.99 X 104
3.00 X 103
2.50 X 10s
3.98 X 103
3.57 X 106
1.76 X 104
1.44 X 10s
5.30 X 105
2.24 X 106
2.91 X 10s
1.39 X 10"
6.09 X 104
3.57 X 10s
3.72 X 106
6.24 X 10"
(dis/s)/g( t = o o )
1.92 X 10s
2.96 X 10s
7.35 X 106
2.54 X 10s
2.09 X 10s
3.62 X 106
7.30 X 10"
2.72 X 106
7.97 X 105
4.91 X 106
7.38 X 105
8.53 X 106
1.54 X 10s
6.92 X 10s
3.72 X 106
4.35 X 10s
Interfering reactions
Ni-60(n,p); Cu-63(n,a);
Mn-55(n,7); Fc-56(n,p);
Ni-S8(n,p)
Co-59(n,7); Cu-63(n,a);
Ni-64(n,7); Zn-68(n,a)
Cu-63(n,7); Zn-64(n,p)
Ge-74(n,7); As-75(n,p);
Se-74(n,p)
Ge-74(n,7); Ge-76(n,2n)
Se-80(n,7); Br-81(n,p);
Kr-78(n,p)
Kr-84(n,7); Rb-85(n.n):
Ni-61(n,d)
Fe-57(n,d)
Ni-61(n,d)
Se-78(n,tt)
; Se-78(n,a)
Kr-84(n,o)
Sr-88(n,a)
to
TABLE II
Atomic No./Element
37-Rb
38-Sr
39-Y
40-Zr
41-Nb
42-Mo
44-Ru
45-Rh
46-Pd
47-Ag
(cont.)
Atomicweightofelement
85.47
87.62
88.905
91.22
92.906
95.94
101.07
102.905
106.4
107.870
Targetisotopicabundance
72.17
9.8
100
51.5
100
9.6
5.5
100
11.8
51.83
Reaction
Rb-85(n,2n)Rb-84m
Sr-86(n,2n)Sr-85m
Y-89(n,2n)Y-88
Y-89(n,n'7)Y-89m
Zr-90(n,2n)Zr-89m
Nb-93(n,2n)Nb-92m
Mo-100(n,2n)Mo-99
Ru-96(n,2n)Ru-95
Rh-103(n,n'7)Rli-103m
Rh-103(n,7)Rh-104m
Pd-110(n, 2n)Pd-109m
Ag-107(n,2n)Ag-106g
Cross-section(mb)
505(34)
247(22)
966(100)
438(44)
86(8)
482(35)
1420(150)
700(100)
216(26)
10(1) X 103
510(35)
870(100)
Half-life
20.5(2) min
67.66(7) min
106.61(2) d
16.06(4) s
4.180(1) min
10.150(2) d
66.02(1) h
1.65(2) h
56.12(1) min
4.34(7) min
4.69(1) min
24.0(1) min
Gammaenergy(keV)
215.6(1)248.0(1)463.6(1)
231.9(1)
898.0(1)1836.0(1)
909.2(1)
587.8(1)
934.5(1)
181.1(1)739.4(1)
336.4(1)
20. IX39.7(1)
51.4(1)97.1(1)
188.9(1)
511.9(1)621.9(1)
270
wa
?ao»
—
Atomic No./Element
Gammas
per
decay
(dis/s)/g(t = 10 min)
(dis/s)/g
(t = 1 h)
ldis/s)/g( t = o o )
Interfering reactions
37-Rb
38-Sr
39-Y
40-Zr
41-Nb
42-Mo
44-Ru
45-Rh
46-Pd
47-Ag
26.459.035.4
84.4
94.099.4
99.1
89.5
99.1
6.0812.1
70.8
6.370.0684
48.23.00
55.7
16.80.312
7.36 X 105
1.62 X 10"
2.95 X 102
2.97 X 106
2.37 X 10s
1.49 X 103
1.50 X 103
1.55 X 10"
1.47 X 10s
4.68 X 107
2.63 X 10s
6.32 X 10s
2.23 X 106
7.64 X 10"
1.77 X 103
2.97 X 106
2.92 X 105
8.88 X 103
8.94 X 103
7.87 X 104
6.62 X 105
5.86 X 107
3.41 X 105
2.07 X 106
2.57 X 106
1.66 X 10s
6.54 X 106
2.97 X 106
2.92 X 10s
3.12 X 106
8.56 X 10s
2.29 X 10s
1.26 X 106
5.86 X 107
3.41 X 105
2.52 X 106
Sr-84(n,p)
Sr-84(n,7)
Zr-90(n,d)
Mo-92(n,a)
Mo-92(n,p)
Mo-98(n,7); Ru-102(n,a)
Pd-104(n,d)
Pd-104(n,p); Ag-107(n,a); Pd-105(n,d)
Pd-108(n,7); Ag-109(n,p); Cd-112(n,a)
Cd-106(n,p)
>
3
TABLE II
Atomic No./Element
47-Ag
48-Cd
49-In
50-Sn
51-Sb
52-Te
53-1
54-Xe
(cont.)
Atomicweightofelement
112.40
1 14.82
118.69
121.75
127.60
126.9044
131.30
Target
isotopic
abundance
(%)
48.17
24.1
95.7
5.64
1.01
57.3
42.7
34.5
100
8.9
Reaction
Ag-107(n,2n)Ag-106m
Ag-109(n,2n)Ag-108g
Cd-1 12(n,2n)Cd-l 1 lm
In-115(n,7)ln-l 16m
In-115(n,n'7)In-l 15m
Sn-124(n,2n)Sn-123m
Sn-112(n,2n)Sn-ll 1
Sb-121(n,2n)Sb-120gd
Sb-123(n,2n)Sb-122m
Te-130(n,2n)Te-129g
I-127(n,7)1-128
I-127(n,2n)I-126
Xe-136(n,2n)Xe-135m
Cross-section(mb)
600(80)
840(150)
725(5O)c
162 300(700)
63(6)
547(23)
1180(120)
1080(90)
731(73)
570(30)
6200(200)
1550(100)
750(50)
Half-life
8.46(10)d
2.37(1) min
48.6(3) min
54.12(5) min
4.486(4) h
40.08(7) min
35.3(8) min
15.89(4)° min
4.21(2) min
69.6(5) min
24.99(2) min
1 3.02(7) d
15.6(1) min
Gammaenergy(keV)
451.0(1)
633.0(1)
150.8(1)245.4(1)
416.9(1)1097.3(2)1293.5(1)
336.2(1)
160.3(1)
762.0(1)1153.0(1)
1171.2(3)
61.4(1)76.1(1)
459.6(1)
442.9(1)
388.6(1)666.3(1)
526.6(1)
toto
WO:D•<3O.OVI
>
Atomic No./Element
Gammasperdecay
(dis/s)/g( t= 10
9.87 X
2.14X
1.24 X
9.79 X
8.02 X
2.49 X
1.08 X
1.08 X
1.25 X
8.80 X
7.12X
2.72 X
1.10 X
min)
102
106
105
107
103
104
104
106
106
104
106
10'
10s
(dis/s)/g( t= 1 h)
5.91 X
2.26 X
5.78 X
4.37 X
4.51 X
1.01 X
4.19 X
2.84 X
1.54X
4.18X
2.39 X
1.63 X
2.85 X
103
106
105
108
10"
105
104
106
106
10s
107
104
105
(dis/s)/g(t = »)
1.74
2.26
9.36
8.14
3.16
1.57
6.05
3.03
1.54
9.28
2.94
7.36
3 06
X
X
X
X
X
X
X
X
X
X
X
X
X
106
106
105
108
105
10s
104
106
106
10s
107
106
10s
Interfering reactions
47-Ag
48-Cd
49-In
50-Sn
28.4
1.75
30.394.0
29.256.284.4
45.8
85.6
51-Sb
52-Te
53-1
54-Xe
1.402.51
1.69
57.519.6
7.14
16.0
32.231.3
80.5
Cd-106(n,p)
Ag-107(n,T); Cd-108(n,p)
Cd-110(n,7); Sn-114(n,a)
Sn-116(n,p); Sn-117(n,d)
Sn-115(n,p); Sn-116(n,d)
Sn-122(n,7); Sb-123(n,p).; Te-126(n,a)
Te-120(n,p)
Sb-121(n,7); Te-122(n,p); Te-123(n,d)
Te-128(n,7); Xe-132(n,a)
Xe-128(n,p); Xe-129(n,d)
Xe-126(n,p)
Xe-134(n,7); Ba-138(n,a)
"0>JO
toI
to
TABLE II (cont.)
Atomic No./Element
55-Cs
56-Ba
57-La
58-Ce
59-Pr
60-Nd
62-Sm
63-Eu
64-Gd
65-Tb
66-Dy
Atomicweightofelement
132.905
137.34
138.91
140.12
140.907
144.24
150.35
151.96
157.25
158.924
162.50
Targetisotopicabundance
100
71.7
99.911
88.5
0.19
100
5.6
3.1
47.9
21.8
100
0.10
Reaction
Cs-133(n,2n)Cs-132
Ba-138(n,2n)Ba-137m
La-139(n,7)La-140
Ce-140(n,2n)Ce-139m
Ce-136(n,2n)Ce-135m+g
Pr-141(n,2n)Pr-140
Nd-150(n,2n)Nd-149
Sm-144(n,2n)Sm-143m
Eu-153(n,2n)Eu-152m
Gd-160(n,2n)Gd-159
Tb-159(n,2n)Tb-158m
Dy-158(n,2n)Dy-157
Cross-section(mb)
1603(100)
1020(70)
8930(40)
963(120)
1600(140)
1660(120)
1906(160)
652(38)
72(6)
1960(180)
450(65)
1950(170)
Half-life
6.974(14)d
2.5513(7) min
40.27(5)h
56.44(48) s
17.76(31) h
3.39(1) min
1.73(1) h
66(2) s
96(1) min
18.56(8) h
10.5(2)s
8.1(l)h
Gammaenergy(keV)
667.5(1)
661.6(1)
328.8(1)487.0(1)
754.2(1)
265.6(1)300.1(1)
Annihilation306.9(2)1596.5(1)
114.3(1)211.3(1)
754.0(2)
89.8(1)
363.6(1)
50.3X5 1 . 7 X
110. (1)
326.2(2)
tdQc
I( .>
Atomic No./Element
Gammasperdecay
(dis/s)/g(t = lOmin)
5.40 X
2.99 X
1.11 X
3.66 X
8.47 X
103
106
10s
106
10'
(dis/s)/g(t = 1 h)
3.23 X
3.20 X
6.60 X
3.66 X
5.00 X
104
106
10s
106
in2
(dis/s)/g(t = °°)
7.26
3.20
3.87
3.66
1.31
X
X
X
X
X
106
106
107
106
104
Interfering reactions
55-Cs
56-Ba
5 7-La
58-Ce
59-Pr
60-Nd
62-Sm
63-Eu
64-Gd
65-Tb
66-Dy
97.4
89.9
20.745.9
92.4
42.422.9
98
0.190.50
19.025.9
89.9
69.9
10.8
7.702.200.881
93.2
6.18 X 106
2.88 X 104
8.10 X 104
9.52 X 103
1.02 X 104
1.71 X 106
1.02 X 102
7.09 X 106
1.47 X 10s
8.11 X 10"
4.81 X 104
6.00 X 10"
1.71 X 106
5.93 X 102
7.09 X 106
4.45 X 105
8.11 X 104
1.37 X 105
1.64 X 106
1.71 X 106
7.23 X 103
Ba-132(n,p)
Ba-136(n,7); Ce-140(n,a); La-138(n,d)
Ce-140(n,p)
Ce-138(n,7); Nd-142(n,a)
•a
90
Nd-148(n,7); Sn-152(n,a)
Eu-151(n,7)
Gd-158(n,7); Tb-159(n,p); Dy-162(n,a)
Dy-158(n,p)
Dy-156(n,7)
TABLE II
Atomic No./Element
66-Dy
67-Ho
68-Er
69-Tm
70- Yb
71-Lu
72-Hf
73-Ta
74-W
(cont.)
Atomicweightofelement
164.930
167.26
168.934
173.04
174.97
178.49
180.948
183.85
Targetisotopicabundance(%)
28.1
100
1.56
100
12.6
97.39
0.16
5.2
99.9877
0.13
Reaction
Dy-164(n,r)Dy-165m
Ho-165(n,2n)Ho-164m
Er-164(n,2n)Er-163
Tm-169(n,2n)Tm-168
Yb-176(n,2n)Yb-175
Lu-175(n,2n)Lu-174m
Lu-175(n,7)Lu-176m
Hf-174(n,2n)Hf-173
Hf-176(n,2n)Hf-175
Ta-181(n,2n)Ta-180m
W-180(n,2n)W-179m
Cross-section(mb)
1.7(0.25) X 106
1211(180)
1820(270)
1971(152)
2150(230)
627(52)
15 100(1240)
1886(145)
2076(150)
1258(50)
490(50)
Half-life
1.257(6) min
37.3(5) min
75.1(4) min
93.1(1) d
4.19(1) d
142(2)d
3.684(6) h
24.0(5) h
70(2)d
8.11(2)h
6.7(3) min
Gammaenergy(keV)
108.2(1)
56.6(1)99.0(1)53.8X436.1(1)1113.5(3)
198.2(1)815.9(1)
282.5(1)396.3(1)
63.OX67.1(1)
88.3(1)
123.7(1)297.0(1)
343.4(1)
63.2X93.3(1)
222.0(1)
to- iO\
©
go
\
Atomic No./Element
66-Dy
67-Ho
68-Er
69-Tm
70-Yb
71-Lu
72-Hf
73-Ta
74-W
Gammasperdecay(%)
3.01
6.670.14
12.50.0280.049
50.046.3
3.086.55
3.107.44
8.86
82.733.8
86.6
11.64.28
8.59
(dis/s)/g(t = 10 min)
1.77 X 109
7.50 X 10s
9.01 X 103
3.64 X 102
1.08 X 103
7.12 X 101
1.56 X 10'
4.85 X 10'
2.50 X 101
5.91 X 104
1.35 X 103
(dis/s)/g(t = 1 h)
1.77 X 109
2.97 X 106
4.35 X 10"
2.18 X 103
6.48 X 103
4.27 X 102
8.66 X 10'
2.90 X 102
1.50 X 102
3.43 X 10s
2.08 X 103
(dis/s)/g(t=oo)
1.77 X 109
4.42 X 106
1.02 X 10s
7.03 X 106
9.43 X 10s
2.10 X 106
5.04 X 107
1.02 X 104
3.64 X 105
4.18 X 106
2.09 X 103
Interfering reactions
Ho-165(n,p); Er-168(n,o)
Er-164(n,p)
Er-162(n,7)
Yb-168(n,p)
Lu-176(n,p); Hf-178(n,a)
Hf-176(n,p); HM77(n,d)
HM74(n,7)
W-180(n,p)
"0
5
K)
TABLE II
Atomic No./Element
74-W
75-Re
76-Os
77-Ir
78-Pt
79-Au
80-Hg
81-Tl
(cont.)
Atomicweightofelement
186.2
190.2
192.2
195.09
196.967
200.59
204.37
Targetisotopicabundance
(%)
28.6
62.60
41.0
37.3
7.2
100
23.1
29.5
Reaction
W-186(n,2n)W-185m
Re-187(n,2n)Re-186g
Os-192(n,2n)Os-191m
Ir-191(n,2n)Ir-190m
Pt-198(n,2n)Pt-197m
Au-197(n,n'-y)Au-197m
Au-197(n,2n)Au-196m
Au-197(n,2n)Au-196m+g
Hg-2OO(n,2n)Hg-199m
Tl-203(n,2n)TI-202
Cross-section(mb)
642(60)
1720(160)
1067(318)
220(26)
910(60)
280(64)
150(20)
2160(35)g
789(120)"
2065(150)
Half-life
1.67(8) min
90.64(9) h
13.10(5) h
3.25(20) h
94.4(8) min
7.86(4) s
9.7(l)h
6.183(10) d
42.6(2) min
12.23(2) d
Gammaenergy(keV)
131.5(1)173.7(1)
63.0X137.2(1)
63.0X71.3X74.4(1)
186.7(l)Df
361.KDD502.6(l)D616.1(2)D
346.5(2)
279.0(1)
147.8(1)188.3(1)
333.0(1)355.7(1)
158.4(1)374.1(1)
439.6(1)
to-J00
as©
1n
>
Atomic No./
Element
74-W
75-Re
76-Os
77-Ir
78-Pt
79-Au
80-Hg
81-T1
Gammasperdecay(%)
4.343.30
1.929.20
4.141.430.074
69.9
95.297.898.5
11.2
70.9
42.537.4
22.986.9
52.513.8
91.4
(dis/s)/g
(t = 10 min)
5.92 X 10s
4.44 X 103
1.22 X 104
8.98 X 103
1.43 X 104
8.56 X 10s
5.43 X 103
5.14X 103
8.22 X 10"
7.06 X 102
(dis/s)/g
( t = l h)
6.01 X 10s
2.65 X 10"
7.14 X 10"
4.94 X 104
7.21 X 10"
8.56 X 105
3.17X 10"
3.08 X 104
3.41 X 10s
4.23 X 103
(dis/s)/g
6.01 X 10s
3.48 X 106
1.39 X 106
2.57 X 105
2.02 X 105
8.56 X 10s
4.59 X 10s
6.60 X 106
5.47 X 10s
1.80 X 106
Interfering reactions
W-184(n,7); Re-185(n,p);
Re-185(n,7); Os-186(n,p)
Os-190(n,7); Ir-191(n,p);
Pt-190(n,p)
Pt-196(n,7); Au-197(n,p);
Hg-198(n,d)
Hg-196(n,p)
Hg-196(n,p)
Os- 188(n, a)
Os-I87(n,d)
Pt-194(n,a)
Hg-200(n,a)
to
to00o
TABLE II (cont.)
Atomic No./Element
82-Pb
90-Th
92-U
Atomicweightofelement
207.19
232.038
238.03
Target
isotopicabundance(%)
1.42
100
99.275
Reaction
Pb-204(n,n'7)Pb-204m
Th-232(n,2n)Th-231
U-238(n,2n)U-237
Cross-section(mb)
51(10)
1259(50)
745(30)
Half-life
66.9(1 )min
25.52(l)h
6.752(2) d
Gammaenergy(keV)
374.7(1)899.2(1)911.7(2)
84.2(1)163.1(1)
101.IX208.0(1)
BO
DY
and C
r
Atomic No./Element
82-Pb
90-Th
92-U
Gammasperdecay
94.299.291.1
6.600.16
23.821.7
(dis/s)/g(t = 10 min)
(dis/s)/g(t = 1 h)
(dis/s)/g(t=oo) Interfering reactions
2.07 X 102 9.75 X 102 2.11 X 103
1.48 X 104 8.76 X 10" 3.27 X 106
1.33 X 103 7.99 X 103 1.87 X 106
Htoi
to
a This cross-section is taken from Refs [2,3].b This cross-section is taken from Ref. [12].c This cross-section contains a contribution from the Cd-111 (n, n'7) reaction.d No transition has been observed between the two states; this may also be the m state.e Must be separated by the half-life taken from Sb-120m.
Gammas from the 9.9(1) min daughter (Os-190m). Intensities are those observed in transient equilibrium.8 The cross-section at 14.70 MeV is taken from Ref. [13] (it is the same as that at 14.5 MeV, within error).11 This cross-section contains a contribution from the Hg-199 (n,n'7) reaction of a cross-section less than 80 mb.
TABLE III. RECOMMENDED (n, 2n) CROSS-SECTIONSto00to
Target nucleus
F-19
P-31
S-36
Ca-48
Sc-45
Sc-45
Ti-46
Cr-50
Cr-52
Mn-SS
Co-59
Co-59
Ni-58
Cu-63
Cu-65
Zn-64
Zn-66
Zn-70
Ga-69
Ga-71
Ge-70
Final nucleus
F-18
P-30
S-35
Ca^»7
Sc-44g
Sc-44m
Ti-45
Cr-49
Cr-51
Mn-S4
Co-58m+g
Co-58m
Ni-57
Cu-62
Cu-64
Zn-63
Zn-65
Zn-69m
Ga-68
Ga-70
Ge-69
o (mb)(Ref. [5])
55(4)
10.5(1. )
-
920(180)
188(14)
149(12)
38(4)
26(3)
304(20)
890(60)
720(50)
402(41)
35(3)
593(36)
926(60)
200(23)
605(55)
754(96)
1007(63)
1085(280)
588(75)
o (mb)(Ref. [4])
49(2)"
12.5(4. )"
20
1000(100)
-
116(23)"
39.4(4)"
20(4)"
357(30)°
809(35)"
788(230)'
473(140)"
30(3)"
550(11)"
968(30)"
178(27)"
690(70)"
-
945(50)"
1146(70)"
605(40)"
Product half-life
109.72(0.06) min
2.498(0.004) min
87.51(0.12) d
4.5401(0.003) d
3.927(0.008) h
2.442(0.004) d
3.08(0.01) h
41.9(0.3) min
27.703(0.004) d
312.2(0.1) d
70.78(0.10) d
9.15(0.10) h
35.99(0.12) h
9.74(0.02) min
12.701(0.002) h
38.1(0.3) min
244.0(0.2) d
13.76(0.02) h
68.1(0.3) min
21.10(0.07) min
39.05(0.10) h
Internal transitionto ground state (%)
98.61
-100
00O:O
»9B.OV>
53
Target nucleus
Ge-72
Ge-76
Ge-76
As-75
Se-74
Se-76
Se-78
Se-80
Se-82
Br-79
Br-81
Br-81
Kr-78
Kr-80
Kr-80
Kr-82
Kr-86
Rb-85
Rb-85
Rb-87
Final nucleus
Ge-71
Ge-75m+g
Ge-75m
As-74
Se-73m
Se-75
Se-77m
Se-79m
Se-81m
Br-78
Br-80g
Br-80m
Kr-77
Kr-79m+g
Kr-79m
Kr-81m
Kr-85m
Rb-84m+g
Rb-84m
Rb-86m+g
o(mb)(Ref. [5])
_
1151(137)
790(80)
970(80)
197(50)
944(66)
<738
680(100)
1008(120)
1070(120)
437(30)
737(74)
721(50)
810(60)
415(50)
160(15)
350(35)
1093(105)
505(34)
1550(150)
o(mb)(Ref. [4])
1022(300)a
1148(120)"
730(100)
1061(100)a
35
879(90)"
800
90
900
974(50)"
-
665(50)a
245(20)
810(60)
415
-
350
1123(100)"
350
1195(180)"
Product half-life
11.8(0.4)d
82.78(0.04) min
47.7(0.7)s
17.79(0.05) d
39.8(1.3) min
119.78(0.01) d
17.4S(0.10)s
3.91(0.05) min
57.28(0.05) min
6.46(0.04) min
17.68(0.02) min
4.42(0.01) h
74.4(0.6) min
35.04(0.10) h
50. (3. )s
13. (1. )s
4.480(0.008) h
32.87(0.1 l )d
20.49(0.17) min
18.82(0.02) d
Internal transitionto ground state (%)
99+
~100
~100
~100
~100
s
IN)00
TABLE III (cont.) 00
Target nucleus Final nucleus a (mb)(Ref. [5])
o (mb)(Ref. [4])
Product half-life Internal transitionto ground state (%)
Rb-87
Sr-84
Sr-86
Sr-88
Y-89
Zr-90
Zv-90
Zr-96
Nb-93
Mo-92
Mo-92
Mo-94
Mo-100
Ru-96
Ru-98
Ru-I04
Rh-103
Pd-102
Pd-108
Pd-110
Pd-110
Rb-86m
Sr-83m+g
Sr-85m
Sr-87m
Y-88
Zr-89m+g
Zr-89m
Zr-95
Nb-92m
Mo-91m+g
Mo-91m
Mo-93m
Mo-99
Ru-95
Ru-97
Ru-103
Rh-102m
Pd-101
Pd-IO7m
Pd-109m+g
Pd-IO9m
584(40)
-
247(22)
246(22)
907(68)
768(78)
80(6)
1529(141)
512(46)
219(19)
17(3)
3(1)
1390(60)
569(30)
790(94)
1230(146)
522(45)
637(45)
448(32)
1884(136)
510(35)
580
1054(100)'
340
318(45)"
966(100)"
764(38)"
86(8)
1400(100)
482(3S)a
192(20)"
14.5
560
1420(150)
700(100)
1050(100)
1440(100)
-
650(60)
500
1500(150)
500
1.020(0.002) min
32.4(0.2) h
67.66(0.07) min
2.81(0.01) h
106.6(0.2) d
78.43(0.08) h
4.18(0.01) min
63.98(0.06) d
10.15(0.02) d
15.49(0.01) min
65.2(0.8) s
6.95(0.05) h
66.02(0.01) h
1.65(0.02) h
2.88(0.04) d
39.35(0.05) d
207. (3. )d
8.47(0.06) h
21.3(0.5)s
13.427(0.014) h
4.69(0.01) min
-100°
94
50
w
o
InCA
~ioo
Target nucleus
Ag-107
Ag-107
Ag-I09
Cd-108
Cd-112
Cd-116
Cd-116
In-113
In-115
In-115
Sn-112
Sn-114
Sn-114
Sn-118
Sn-120
Sn-122
Sn-124
Sn-124
Sb-121
Sb-121
Sb-123
Final nucleus
Ag-106g
Ag-106m
Ag-IO8g
Cd-107
Cd-lllm
Cd-115g
Cd-115m
In-112m
In-114g
In-114m
Sn-111
Sn-ll3m+g
Sn-113m
Sn-117m
Sn-119m
Sn-121g
Sn-123g
Sn-123m
Sb-120g
Sb-120m
Sb-122m+g
o(mb)(Ref. (5J)
870(100)
600(80)
840(150)
915(85)
725(50)
830(80)
790(80)
1317(200)
269(20)
1515(100)
1275(100)
1239(130)
-
966(100)
1444(210)
875(135)
900(180)
547(23)
1080(90)
427(20)
1542(80)
0 (mb)(Ref. [4])
937(280)*
400
-
-
675
-
820
790
-
1223(120)a
1180(120)*
1300(200)
1050
1200
-
-
-
-
-
610
1420(140)a
Product half-life
24.0(0.1) min
8.46(0.10) d
2.37(0.01) min
6.50(0.02) h
48.6(0.03) min
53.46(0.10) h
44.6(0.3) d
20.9(0.2) min
71.9(0.!)s
49.51(0.01) d
35.3(0.8) min
115.10(0.17) d
21.4(0.4) min
14.0(0.3) d
293.0(1.3) d
27.06(0.04) h
129.2(0.4) d
40.08(0.07) min
15.89(0.04) min
5.76(0.02) d
2.681(0.003) d
Internal transitionto ground state (%)
~0
9C
~0
96.7
91
~0
~0
~0
-100
i
00
TABLE III (cont.)
Target nucleus
Sb-123
Te-t20
Te-120
Te-122
Te-122
Te-124
Te-128
Te-128
Te-130
Te-130
1-127
Xe-124
Xe-126
Xe-126
Xe-128
Xe-128
Xe-130
Xe-132
Xe-134
Xe-136
Xe-136
Final nucleus
Sb-122m
Te-U9g
Te-119m
Te-121g
Te-121m
Te-123m
Te-127g
Te-127m
Te-129g
Te-129m
1-126
Xe-123
Xe-125m+g
Xe-125m
Xe-127m+g
Xe-I27in
Xe-129m
Xe-I31m
Xe-133m
Xe-135m+g
Xe-135m
a(mb)(Ref. [5])
731(73)
68S(80)
535(85)
725(40)
890(100)
980(100)
780(60)
940(100)
570(30)
885(45)
1649(80)
997(80)
1480(130)
410(125)
1446(140)
317(25)
1435(130)
775(65)
665(80)
-
750(50)
a(mb)(Ref. [4])
1000
-
-
-
700
-
-
900
-
1000
1550(100)a
1200(100)
1400(100)
700
1550(150)
840
-
770
665
1750(100)
750
Product half-life
4.21(0.02) min
16.05(0.05) h
4.68(0.05) d
16.78(0.35) d
154. (7. )d
119.7(0.1) d
9.35(0.07) h
109. (2. )d
69.5(0.5) min
33.52(0.12) d
13.02(0.07) d
2.08(0.02) h
17.3(0.4) h
57. (1. )s
36.4(0.1) d
69.2(0.9) s
8.89(0.02) d
1 1.770(0.012) d
2.19(0.03) t)
9.1O4(O.O2O)h
15.65(0.10) min
Internal transitionto ground state (%)
~ 0
90
97.6
63
~100
~100
99+
286
w©«<
1oen
Target nucleus
Cs-133
Ba-132
Ba-134
Ba-136
Ba-138
Ce-136
Ce-138
Ce-140
Ce-140
Ce-142
Pr-141
Nd-142
Nd-142
Nd-148
Nd-150
Sm-144
Sm-I44
Sm-154
Eu-151
Eu-153
Eu-153
Final nucleus
Cs-132
Ba-131
Ba-133m
Ba-135m
Ba-137m
Ce-135m+g
Ce-137m
Ce-139m+g
Ce-139m
Ce-141
Pr-140
Nd-14lm+g
Nd-I41m
Nd-147
Nd-149
Sm-l43m+g
Sm-143m
Sm-153
Eu-150m
Eu-152m,
Eu-152m2
o(mb)(Ref.(5J)
1620(150)
1576(100)
783(56)
<1150
1020(70)
1604(148)
974(88)
1810(85)
900(120)
1774(140)
1710(120)
1692(120)
591(45)
1950(150)
1906(160)
1678(185)
652(38)
1882(130)
467(43)
-
72(6)
o(mb)(Ref. [4])
1603(100)*
1600(100)
940
700
1250
1600(140)
970(90)
175O(7O)a
963(120)a
1760(70)a
1660(120)a
1701(120)a
600(50)
1710(500)"
169O(50O)a
1488(450)a
-
1870(550)"
-
500(100)
70
Product half-life
6.474(0.014) d
12.0(0.1) d
38.9(0.1) h
28.7(0.2) h
2.554(0.002) min
17.76(0.31) h
34.4(0.4) h
137.65(0.03) d
56.44(0.48) s
32.50(0.01) d
3.39(0.01) min
2.50(0.08) h
61.5(2.0) s
10.98(0.01) d
1.73(0.01) h
8.83(0.01) min
65. (3. ) s
46.8(0.1) h
12.55(0.05) h
9.32(0.01) h
96. (1. ) min
Internal transitionto ground state (%)
~100d
~100
99.97
99.8
0.0e
00
TABLE III (cont.) OOOO
Target nucleus
Gd-152
Gd-154
Gd-160
Tb-159
Dy-156
Dy-158
Dy-160
Ho-165
Er-162
Er-164
Er-166
Er-168
Er-170
Tm-169
Yb-168
Yb-170
Yb-176
Lu-175
Hf-174
Hf-176
Hf-179
Final nucleus
Gd-15l
Gd-153
Gd-159
Tb-158m
Dy-155
Dy-157
Dy-159
Ho-164m
Er-161
Er-163
Er-165
Er-167m
Er-169
Tm-168
Yb-167
Yb-169
Yb-175
Lu-174m
Hf-173
Iif-175
Hf-I78m
o(rab)(Ref. [5])
1867(233)
1995(280)
1975(185)
451(65)
1852(143)
1990(167)
2020(218)
1211(180)
1927(130)
1824(270)
1954(147)
690(110)
1900(135)
1971(152)
1913(217)
1985(151)
2166(230)
627(52)
1886(145)
2076(150)
-
o (mb)(Ref. [4])
1800(200)
1900(150)
1960(180)
450(65)
1850(150)
1950(170)
2000(200)
1050(300)a
1900(130)
1820(270)
1960(150)
1000
1930(130)
2070(600)*
1920(150)
1940(150)
2150(230)
558(17O)a
1900(150)
2050(150)
900
Product half-life
120. ;20. )d
241.6(0.2) d
18.56(0.08) h
10.5(0.2) s
10.0(0.3) h
8.06(0.08) h
144.4(0.2) d
37.5(1.0) min
3.24(0.04) h
75.0(0.4) min
10.34(0.05) h
2.28(0.03) s
9.40(0.02) d
9 3 . 1 ( 0 . 1 ) d
17.7(0.2) min
32.022(0.008) d
4.19(0.01)d
142. (2. )d
24.0(0.5) h
70. (2. )d
4.3(0.1 )s
Internal transitionto ground state (%)
esO:O
p
g.O
Target nucleus
Hf-180
Ta-181
W-180
W-180
W-182
W-184
W-186
W-186
Re-185
Re-185
Re-187
Os-184
Os-186
Os-192
Os-192
Ir-191
Ir-191
lr-193
Pt-192
Pt-196
Pt-198
Final nucleus
Hf-179m
Ta-180m
W-179m+g
W-179m
W-181
W-183m
W-185m+g
W-185m
Re-184g
Re-184m
Re-186g
Os-183m
Os-185
Os-191m+g
Os-19lm
Ir-190g
lr-l90m
lr-192
Pt-191
Pt-I95m
Pt-197m+g
o (mb)(Ref. [5])
_
1150(100)
1866(176)
490(45)
2162(140)
790(90)
2272(250)
642(60)
1430(220)
260(100)
1720(160)
488(39)
2000(120)
1993(200)
1067(318)
1716(125)
220(26)
2062(121)
2026(168)
460(55)
-
o (mb)(Ref. (4))
600
1258(5O)a
2100(600 )a
490(50)
2O2O(6OO)a
1600
1840(550)a
600(60)
1500(450)a
300(90)a
1700(200)
-
-
2120(150)
-
-
370
2048(1 50)a
2030(100)
460
2300(200)
Product half-life
18.67(0.04) s
8.00(0.05) h
37.5(0.5) min
6.4(0.1) min
120.95(0.02) d
5.4(0.1)s
75.1(0.3) d
1.67(0.03) min
38.0(0.5) d
169. (8. )d
90.64(0.09) h
9.9(0.3) h
93.6(0.5) d
15.4(0.1) d
13.10(0.05) h
11.78(0.10) d
3.2(0.2) h
74.1(0.2) d
2.9(0.1) d
4.020(0.009) d
18.3(0.3) h
Internal transitionto ground state (%)
99.69
~100
75
~100 f
- 1 0 0
5g
97
00O
TABLE III (cont.)
O
Target nucleus
Pt-198
Au-197
Au-197
Hg-196
Hg-198
Hg-200
Hg-204
Tl-203
Pb-204
Pb-204
Th-232
U-238
Final nucleus
Pt-197m
Au-196m+g
Au-196m
Hg-195m
Hg-197m
Hg-I99m
Hg-203
TI-202
Pb-2O3m+g
Pb-2O3m
Th-231
U-237
0 (mb)(Ref. [5])
910(60)
-
150(20)
1617(160)
910(85)
789(120)
2030(140)
1950(200)
-
860(180)
1320(130)
703(50)
a (mb)(Ref. [4])
1200
21O0(15O)a
133(40)a
-
-
-
1924(550)a
2065(150)a
2103(200 )a
1200
1259(50)a
745(30)a
Product half-life
94.4(0.8) min
6.183(0.010) d
9.7(0.1) h
40.0(0.5) h
23.8(0.1) h
42.6(0.2) min
46.585(0.008) d
12.23(0.02) d
52.02(0.05) h
6.09(0.10) s
25.52(0.03) h
6.75(0.01) d
Internal transitionto ground state (%)
~100
-100
' This is a value of the respective excitation function at 14.5 MeV.b The half-life of Sr-83m is 4.95(0.15) s.c The half-life of Ag-108m is 127. (21. ) years.d The half-life of Ce-135m is 20. (2. ) s.e Internal transition to the mi state.f The half-life of Re-186m is 2 X 10s years.8 The 3.2 h half-life state decays partially to the ground state across an intermediate state with a 1.2 h half-life.
00
§
O• 2
TABLE IV. RECOMMENDED (n, p) CROSS-SECTIONS
Target nucleus
N-15
0-16
0-17
F-19
Ne-20
Na-23
Mg-24
Mg-25
Mg-26
Al-27
Si-28
Si-29
Si-30
P-31
S-32
S-33
S-34
S-36
Cl-35
Cl-37
Final nucleus
C-15
N-16
N-17
0-19
F-20
Ne-23
Na-24
Na-25
Na-26
Mg-27
Al-28
Al-29
Al-30
Si-31
P-32
P-33
P-34
P-36
S-35
S-37
o(mb)(Ref. [5])
38(3)
35(4)
5.5(2. )
19(2)
-
35(4)
181(8)
56(6)
39(11)
75(4)
226(30)
129(15)
95(20)
97(15)
254(25)
134(22)
78(8)
-
125(15)
28(3)
o (mb)(Ref. [4p
16(4)
40(3)a
35
20(2)a
92
44(13)a
188(8)a
45(13)a
25(5)
74(22)a
256(20)a
115(15)
-
88(4)a
230(70)a
190(57)a
73(10)a
50
110(10)
20(5)
Product half-life
2.449(0.004) s
7.13(0.02) s
4.173(0.004) s
26.76(0.08) s
10.996(0.020) s
37.24(0.12) s
15.020(0.007) h
59.6(0.7) s
1.072(0.009) s
9.462(0.011) min
2.2406(0.0005) min
6.56(0.06) min
3.60(0.06) s
2.622(0.005) h
14.26(0.04) d
25.34(0.12) d
12.43(0.08) s
3. s
8 7 . 5 1 ( 0 . 1 2 ) d
5.05(0.02) min
Internal transitionto ground state (%)
s
VO
TABLE IV (cont.)
Target nucleus
Ar-38
Ar-40
K-41
Ca-42
Ca-43
Ca-44
Ca-46
Sc-45
Ti-46
Ti-46
Ti-47
Ti-48
Ti-49
Ti-50
V-51
Cr-52
Cr-53
Cr-54
Mn-55
Fe-54
Fe-56
Final nucleus
Cl-38
Cl-40
Ar-41
K-42
K-43
K-44
K-46
Ca-45
Sc-46m+g
Sc-46m
Sc-47
Sc-48
Sc-49
Sc-50
Ti-51
V-52
V-53
V-54
Cr-55
Mn-54
Mn-56
a(mb)(Ref. [5])
75(1.5)
16(2)
51(8)
178(12)
101(13)
46(5)
-
57(6)
-
48(8)
116(15)
53(6)
23(5)
12(2)
33(3)
80(6)
48(7)
18(3)
57(7)
332(30)
98(7)
a (mb)(Ref. [4])
100(20)
18
43(5)a
153(2O)a
100(10)
39(4)a
52(15)a
58(6)a
242(30)a
-
107(15)a
66(6)a
29.5(5. )a
16.5(3. )a
31.5(3)a
102(20)a
43(5)
16(3)
44(13)a
365(30)"
106(30)a
Product half-life
37.24(0.05) min
1.32(0.2) min
1.827(0.007) h
12.360(0.003) h
22.3(0.1) h
22.13(0.19) min
107. (10. )s
165.1(0.7) d
83.83(0.02) d
18.72(0.06) s
3.422(0.004) d
43.67(0.09) h
57.00(0.18) min
1.71(0.01) min
5.80(0.03) min
3.746(0.007) min
1.60(0.05) min
43. (3. )s
3.52(0.03) min
312.2(0.1) d
2.5785(0.0006) h
Internal transitionto ground state (%)
~100
to
OO
Target nucleus
Fe-57
Fe-58
Co-59
Ni-58
Ni-58
Ni-60
Ni-61
Ni-62
Ni-62
Cu-65
Zn-64
Zn-66
Zn-67
Zn-68
Ga-69
Ga-69
Ga-71
Ga-71
Ge-70
Ge-72
Ge-73
Final nucleus
Mn-57
Mn-58
Fe-59
Co-58m+g
Co-58m
Co-60m
Co-61
Co-62g
Co-62m
Ni-65
Cu-64
Cu-66
Cu-67
Cu-68m
Zn-69g
Zn-69m
Zn-71g
Zn-71 m
Ga-70
Ga-72
Ga-73
a (mb)(Ref. [5])
55(4)
7(1.5)
73(10)
375(22)
190(18)
95(10)
95(10)
-
21(2.5)
27(5)
160(12)
72(8)
38(6)
16.5(2.5)
38(5)
26(2)
8(1)
12.5(1.5)
73(8)
31(3)
27(4)
a(mb)(Ref. [4])
56(16)a
17(5)
60(10)a
378(110)a
147(44)a
59(18)a
85(25)a
22(7)a
22(7)a
25(5)a
164(10)a
68(13)a
45(5)
-
34(3)
25(2)a
12(4)
11(1)
77(23)a
41(12)a
22(7)a
Product half-life
1.54(0.05) min
65.3(0.7)s
45.54(0.05) d
70.78(0.10) d
9.15(0.10) h
10.47(0.04) min
1.650(0.005) h
1.50(0.04) min
13.91(0.05) min
2.520(0.001 )h
12.701(0.002) h
5.10(0.02) min
62.01(0.14) h
3.75(0.05) min
55.6(1.6) min
13.76(0.02) h
2.45(0.10) min
3.94(0.05) h
21.10(0.07) min
14.10(0.2) h
4.87(0.03) h
Internal transitionto ground state (%)
~100
~ 0
99+
~ 0
H
TABLE IV (cont.)
Target nucleus
Ge-74
As-75
As-75
Se-74
Se-76
Se-77
Se-78
Se-80
Br-79
Br-81
Kr-80
Kr-82
Kr-83
Rb-87
Sr-84
Sr-84
Sr-86
Sr-88
Y-89
Zr-90
Zr-91
Final nucleus
Ga-74
Ge-75m+g
Ge-75m
As-74
As-76
As-77
As-78
As-80
Se-79m
Se-81m
Br-80m
Br-82
Br-83
Kr-87
Rb-84m+g
Rb-84m
Rb-86m+g
Rb-88
Sr-89
Y-90m+g
Y-91m+g
o (mb)(Ref. [5])
11(2)
29(2.5)
16(1.5)
134(13)
75(6)
35(5)
17(2)
16(4)
10(3)
15(2)
55(9)
23(4)
14(3)
12(1.3)
96(8)
47(7)
44(4)
13.5(1.5)
28(6)
-
29(4)
o (mb)(Ref. [4])
12(4)a
19.2(2)a
18
147(30)a
55(5)
35(5)
18(4)
10
15(2)
-
23(4)
-
10(2)
96(8)
47(7)
44.5(4)a
15(2)a
24.6(3)a
45(3)a
32.5(3)a
Product half-life
8.25(0.05) min
82.78(0.04) min
47.7(0.7) s
17.79(0.05) d
26.37(0.07) h
38.83(0.05) h
90.7(0.2) min
15.2(0.2) s
3.91(0.05) min
57.28(0.05) min
4.42(0.01) h
35.30(0.03) h
2.39(0.03) h
76.31(0.62) min
32.87(0.1 l )d
20.49(0.17) min
18.82(0.02) d
17.78(0.11) min
50.55(0.09) d
64.06(0.11) h
58.51(0.06) d
Internal transitionto ground state (%)
99+
~100
~100b
99+c
-100
60O=O<
o
Target nucleus
Zr-91
Zr-92
Zr-94
Mo-92
Mo-95
Mo-95
Mo-96
Mo-97
Mo-98
Ru-96
Ru-96
Ru-99
Ru-100
Ru-101
Rh-103
Pd-104
Pd-105
Pd-105
Pd-106
Ag-107
Ag-109
Final nucleus
Y-91m
Y-92
Y-94
Nb-92m
Nb-95m+g
Nb-95m
Nb-96
Nb-97m+g
Nb-98g
Tc-96m+g
Tc-96m
Tc-99m
Tc-lOO
Tc-101
Ru-103
Rh-104m
Rh-105m+g
Rh-105m
Rh-106g
Pd-107m
Pd-109m+g
a(nib)(Ref. [5])
14.2(1.2)
19.5(2.5)
11(1)
60(5)
31(4)
-
19(2)
14(1.8)
-
170(30)
-
<16
15(6)
-
17(3)
31(6)
31(3)
23(8)
16(4)
15(2)
10(3)
a (mb)(Ref. [4])
14(2)
18.5(5.5)a
9.6(2.8)a
64(19)a
38(1 l)a
24
2O.3(6)a
12.5(3.7)a
11(4)
150(20)
62
15
-
36(4)
16(1)
-
38(8)
-
-
15
14(2. l)a
Product half-life
49.71(0.04) min
3.54(0.01) h
18.7(0.1) min
10.15(0.02) d
35.05(0.10) d
86.6(0.8) h
23.35(0.05) h
72.1(0.7) min
2.86(0.06) s
4.28(0.07) d
51.5(1.0) min
6.007(0.002) h
15.8(0.1) s
14.2(0.1) min
39.35(0.05) d
4.41(0.02) min
35.36(0.06) h
45. s
29.80(0.08) s
21.3(0.5) s
13.427(0.014)11
Internal transitionto ground state (%)
97.5
~100d
~ 0 e
98
~100
~ 0 f
~100g to
TABLE IV (cont.)
to
Target nucleus
Cd-106
Cd-106
Cd-110
Cd-110
Cd-111
Cd-112
In-115
Sn-116
Sn-117
Te-122
Xe-128
Nd-142
Nd-143
Sm-144
Ho-165
Final nucleus
Ag-106g
Ag-106m
Ag-llOg
Ag-llOm
Ag-11 lm+g
Ag-112
Cd-115g
In-116m
ln-117g
Sb-122m+g
1-128
Pr-142m+g
Pr-143
Pm-144
Dy-16Sm+g
o(mb)(Ref. [5])
76(24)
54(20)
23(4)
-
19(2)
12(2)
18(4)
11(1.3)
10(1.2)
10.5(1.5)
27(4)
13(2)
11(2)
19(4)
-
a (mb)(Ref. [4])
_
76
27(5)
20
22(5)a
16(2)
15(5)
11
-
12(2)
-
14(2)
12(2)
-
40(12)a
Product half-life
24.0(0.1) min
8.46(0.10) d
24.42(0.14) s
249.8(0.1) d
7.45(0.01) d
3.14(0.02)h
53.46(0.10) h
54.15(0.06) min
43.8(0.7) min
2.681(0.003) d
24.99(0.02) min
19.2(0.1) h
13.59(0.04) d
363. (14. )d
2.334(0.006) h
Internal transitionto ground state (%)
~ 0
1.5
99.7h
~ 0 '
47*
~100k
-1001
97.76m
WO:O<
a.o
E
a This is a value of the respective excitation function at 14.5 MeV.b The half-life of Rb-86m is 1.020(0.002) min.c The half-life of Y-90m is 3.19(0.01) h.d The half-life of Nb-97m is 60. (8. ) s.e The half-life of Nb-98m is 51.3(0.3) min.f The half-life of Rh-106m is 130. (2. ) min.8 The half-life of Pd-109m is 4.69(0.01) min.h The half-life of Ag-111 m is 64.8(0.8) s.' The half-life of Cd-115m is 44.6(0.3) d.' The half-life of In-117m is 1.93(0.02) h and a(n,p) leading to this isomeric state is approximately 6.5 mb.k The half-life of Sb-122m is 4.21 (0.02) min.1 The half-life of Pr-142m is 14.6(0.5) min.m The half-life of Dy-165m is 1.257(0.006) min.
"8
TABLE V. RECOMMENDED (n,a) CROSS-SECTIONS00
Target nucleus
F-19
Na-23
Mg-26
Al-27
Si-30
P-31
S-34
S-36
CI-35
Cl-37
Ar-40
K-41
Ca-40
Ca-44
Ca-46
Sc-45
Ti-48
V-51
Cr-54
Mn-55
Fe-54
Final nucleus
N-16
F-20
Ne-23
Na-24
Mg-27
Al-28
Si-31
Si-33
P-32
P-34
S-37
Cl-38m+g
Ar-37
Ar-41
Ar-43
K-42
Ca-4S
Sc-48
Ti-51
V-52
Cr-51
a(mb)(Ref. [5])
15(5)
150(30)
77(8)
121(6)
70(10)
118(15)
138(35)
-
117(15)
36(10)
10.0(1.5)
39(8)
138(20)
35(6)
-
56(6)
31(3)
16(1)
14(1.2)
32(5)
100(10)
o (mb)(Ref. (4])
33(7)"
150(15)"
75(22)a
119(36)a
89(27)"
110(10)*
134(67)"
15
117(10)"
45(13)a
11.3(2.0)"
33.5(2)"
115(35)"
36(5)"
21(6)"
55(5)"
40(12)"
16(2)"
12.4(3.7)"
29(9)"
119(20)"
Product half-life
7.13(0.02) s
10.996(0.020) s
37.24(0.12) s
15.020(0.007) h
9.462(0.011) min
2.2406(0.0005) min
2.622(0.005) h
6.18(0.18) s
14.26(0.04) d
12.43(0.08) s
5.05(0.02) min
37.24(0.05) min
35.04(0.04) d
1.827(0.007) h
5.37(0.06) min
12.360(0.003) h
165.1(0.7) d
43.67(0.09) h
5.80(0.03) min
3.746(0.007) min
27.703(0.004) d
Internal transitionto ground state (%)
~100b
WO:©
nV)
Target nucleus
Fe-58
Co-59
Ni-62
Cu-63
Cu-65
Zn-68
Ga-69
Ga-71
Ge-76
As-7S
Br-79
Sr-88
Mo-92
Rh-103
Ag-107
Cd-106
Nd-144
Final nucleus
Cr-55
Mn-56
Fe-59
Co-60m
Co-62m
Ni-65
Cu-66
Cu-68
Zn-73
Ga-72
As-76
Kr-85m
Zr-89m+g
Tc-100
Rh-104m
Pd-103
Ce-141
o(mb)(Ref. [S])
21(2)
30(2)
20(3)
23(3)
16(4)
9(1)
34(4)
-
-
10(1)
16(2)
75(30)
22(3)
11(2)
-
-
10(1)
a(mb)(Ref. [4])
21(6)a
29(2)a
21(3)a
21(6)a
7.2(2.1)"
11.6(2.3)a
18(2)
60(4)
14(4)a
11.6(l)a
12.0(1.8)"
-
25(3)
11(2)
ll.3(3.4)a
100(40)
-
Product half-life
3.52(0.03) min
2.5785(0.0006) h
45.54(0.05) d
10.47(0.04) min
13.91(0.05) min
2.520(0.001) h
5.10(0.02) min
31. (1. )s
23.5(1.0) s
14.10(0.2) h
26.37(0.07) h
4.480(0.008) h
78.43(0.08) h
15.8(0.1) s
4.41(0.02) min
16.96(0.02) d
32.50(0.01) d
Internal transitionto ground state (7c)
94C
a This is a value of the respective excitation function at 14.5 MeV.b The half-life of Cl-38m is 0.715(0.003) s.c The half-life of Zr-89m is 4.18(0.01) min.
to
300 BODY and CSIKAI
Now, while the result for Nm (Eq. (7a)) is just the same as that for N (Eq. (3)),Ng is a rather complicated function of the parameters and of time. However, thereare limiting cases where Ng is proportional either to (am + ag) or to ag.Asymptotically, Ng will always be proportional to (fiom + ag), but one can only usethis fact to advantage if either Xm > Xg or Xg > Xm. In the former case, if it isalso true that 0 = 1 (IT « 100%), one can use the (am + ag) 'total' cross-sectionin calculating ground state activity. Now, of course, a cooling time of t c > T™2
has to be chosen in order to obtain exponential decay. On the other hand, ifXg > Xm and, in addition, the inequality omfikmt < a% also holds, then one canuse ag for the same purpose. A short cooling time ( t c < T™2) is appropriate. InTables III-V the (am + ag) or the ag values are presented according to whetherthe final nucleus is denoted either by X - A m + or X — A , respectively, whereA is the mass number and X is the symbol of the element. If neither of theinequalities between Xm and Xg hold, then no cross-section (involving the groundstate) is given, unless |3 * 0 (that is, unless the two states are totally separated fromeach other).
However, it has to be noted that the use of ground state activity (if ametastable state is also present) should be carried out with care or, preferably, beavoided whenever a proper substitution is possible.
3. EXPLANATION OF THE NUCLEAR DATA IN TABLE II
Details on the origins of the data in Table II, as well as on the errors, aresummarized as follows. The (n, 2n), (n, p) and (n, a) cross-sections are eitherfrom Refs [4] or [5]. The (n, n'7) cross-sections are from Ref. [5] in every case,while the thermal (n,7) cross-sections are from Ref. [7].
The cross-sections, except (n,7), are determined nominally at a neutronenergy of 14.5 MeV. Data for isotopic abundances were taken from Ref. [8],half-life data from Ref. [9] and gamma energies and intensities from Ref. [10].Errors in the last digit(s) of the half-life values are placed within parentheses, asare the energy errors: the uncertainty is in the last digit of the energy value(0.1 keV is the minimum error by definition). The energy errors may be replacedby the symbol X for an X-ray of known intensity which is associated with thedecay of the nuclide.
The 'Gammas per decay' column denotes the number of photons emitted in100 decays of the nuclide. Here the number of digits given is a measure of theaccuracy of the value, i.e. a three-digit figure (e.g. 90.1 or 9.23) signifies anuncertainty of <10%, while a two-digit figure (90 or 9.2) signifies an uncertaintyof between 10 and 20%. A one-digit figure (9., 0.9, 0.09) signifies a level of 20% orgreater uncertainty. Further information (e.g. for IT values) can be found inTables III-V.
PART 2-2 301
4. EXPLANATION OF THE CROSS-SECTION TABLES
The (n, 2n), (n, p) and (n, a) cross-sections are given in Tables III, IV and V,respectively. They are the recommended values of Bychkov et al. ([4] or [6]), as wellas of Qaim [5]. The cross-sections are assigned nominally to 14.5 MeV. However,this energy value (which is not the best one from the point of view of the measuringtechnique) is of use only in some of the cases, i.e. where a great deal of independentexperimental data are available or an excitation function has been measured (markedby superscript 'a' in column 4 of Tables III—V). In some cases, measurements at14.1 or 14.8 MeV are also included.
The tables present cross-section values (based on experimental data) only incases where the following two conditions are both fulfilled:
(1) The half-life of the product nucleus is within the one second and the one yearinterval.
(2) The cross-section (according to at least one of the references) is greater than10 mb.
The half-lives in these tables are very recent and are taken from Ref. [11]. Thevalues of the internal transitions (leading to the ground state) are taken fromRef. [9]. The 'Product half-life' column presents the ground state value wheneverthe final nucleus is either X - A m + g or X - A g .
TABLE VI. SOME VERY PRECISE CROSS-SECTIONS AT 14.7 MeV FROMA SIMULTANEOUS EVALUATION( The proton scattering cross-section of hydrogen is also included because it is afrequently used standard. The data were taken from Refs [12,13].)
Reaction
Al-27(n,a)Na-24
Fe-56(n,p)Mn-56
Cu-63(n, 2n)Cu-62
Cu-65(n, 2n)Cu-64
Au-197(n,2n)Au-196m+g
Nb-93(n, 2n)Nb-92m
S-32(n,p)P-32
H-l(n,n)H-l
Cross-section(mb)
113.7
107.8
537
962
2160
451
215
650
Uncertainty(%)
0.6
0.6
1.2
1.2
1.6
1.6
1.5
1.4
302 BODY and CSIKAI
TABLE VII. ISOTOPIC AND ELEMENTAL CROSS-SECTIONS AT14.7 MeV FROM A RECENT EVALUATION [14]
Reaction
Al-27(n,p)Mg-27
Si(n, X)Al-28
Ti(n, X)Sc-46
Ti(n, X)Sc-47
Ti(n, X)Sc-48
V-51(n,p)Ti-51
V-51(n,a)Sc-48
Cr(n, X)V-52
Mn-55(n,a)V-52
Mn-55(n, 2n)Mn-54
Fe(n,X)Mn-54
Fe-54(n,a)Cr-51
Co-59(n,p)Fe-59
Co-59(n,a)Mn-56
Co-59(n, 2n)Co-58
Cu-65(n,p)Ni-65
Zn(n, X)Cu-64
Zn-64(n,2n)Zn-63
Isotopiccross-sectionsa
(mb)
70.5
257.3
294.8
223.1
60.6
31.87
15.89
72.49
31.21
816.7
284.4
87.9
56.60
30.17
747.7
20.46
165.4
162.2
Elementalcross-sections(mb)
Same
237.3
24.18
16.51
44.67
31.79
15.85
60.74
Same
Same
16.50
5.096
Same
Same
Same
6.303
80.4
78.8
Standarddeviation(%)
2.0
2.5
2.3
17.2
2.4
4.4
2.4
4.4
4.2
2.6
2.0
2.7
16.2
1.4
2.4
7.0
2.6
2.4
Calculated by assuming that the yield is attributed to that single isotope which isresponsible for the dominant portion of the yield.
Finally, it should be mentioned that it is not too essential whether data fromRefs [4] or [5] are used. The difference between these two sets of data is greaterthan their summed errors in about 8% of all cases, while this number is reduced to1.4% if only those data are included which were taken from excitation functions(Refs [4,6 ]). Therefore, a preference for the value of Bychkov et al. is suggested ifthis value is taken from an excitation function (although the errors seem to beslightly overestimated here in some cases).
The results of a simultaneous evaluation of some important cross-sectionsat 14.7 MeV are presented in Table VI. These are very precise values and areused frequently as standards [12, 13]. In Table VII, some cross-sections — alsomeasured at 14.7 MeV — are given from a recent evaluation, including elementalcross-sections [14].
PART 2-2 303
ACKNOWLEDGEMENTS
The authors are very much indebted to H. Vonach for his useful remarks.
REFERENCES
[1] CSIKAI, J., At. Energy Rev. 11 3(1973)415.[2] TAGESEN, S., VONACH, H., Physics Data, Vol. 13-1, Fachinformationszentrum,
Karlsruhe (1981).[3] VONACH, H., "The 27Al(n,a) cross-section", Nuclear Data Standards for Nuclear
Measurements, Technical Reports Series No. 227, IAEA, Vienna (1983) 59.[4] BYCHKOV, V.M., MANOKHIN, V.N., PASHCHENKO, A.B., PLYASKIN, V.I., Cross
sections for neutron induced threshold reactions, Energoizdat, Moscow (1982) (in Russian).2
[5] QAIM, S.M., "14 MeV neutron activation cross sections", Handbook of Spectroscopy,Vol. 3, CRC Press, Boca Raton, FL( 1981) 141.
[6] MANOKHIN, V.N., PASHCHENKO, A.B., PLYASKIN, V.I., BYCHKOV, V.M.,PRONYAEV, V.G., Chapter 2-3, this Handbook.
[7] GRYNTAKIS, E.M., MUNDY, G., CULLEN, D.E., Part 2-1, this Handbook.[8] YOSHIZAWA, Y., HARIGUCHI, T., YAMADA, M., Chart of the Nuclides, Tokai,
Ibaraki(1980).[9] Table of Isotopes, 7th edn (LEDERER, CM., SHIRLEY, V.S., Eds) Wiley, New York
(1978).[10] REUS, U., WESTMEIER, W., At. Data Nucl. Data Tables 29 2 (1983) 205.[11] LORENZ, A., Nuclear Data Section, IAEA, private communication, 1984.[12] WINKLER, G., RYVES, T.B., Ann. Nucl. Energy 10 (1983) 601.[13] RYVES, T.B., "A simultaneous evaluation of some important cross-sections at 14.70 MeV",
Nuclear Standard Reference Data (Proc. IAEA-OECD/NEANDC Advisory GroupMeeting Geel, Belgium, 1984), IAEA-TECDOC-335, IAEA, Vienna (1985) 431.
[141 EVAIN, B.P., SMITH, D.L., LUCCHESE, P., Argonne National Lab., IL,Rep. ANL/NDM-89( 1985).
2 If an excitation function is presented in Ref. [6], then this value is accepted instead ofa value from Ref. [4], even in the case when the new error is greater than the old one.
2-3. ACTIVATION CROSS-SECTIONSINDUCED BY FAST NEUTRONS
V.N. MANOKHIN, A.B. PASHCHENKO,V.I. PLYASKINInstitute of Physics
and Power Engineering,Obninsk,Union of Soviet Socialist Republics
V.M. BYCHKOV*Department of Safeguards,International Atomic Energy Agency,Vienna
V.G. PRONYAEV*Nuclear Data Section,Division of Research and Laboratories,International Atomic Energy Agency,Vienna
Abstract
ACTIVATION CROSS-SECTIONS INDUCED BY FAST NEUTRONS.Evaluated cross-sections for the most important activation reactions induced by fast
neutrons have been compiled on the basis of internationally available evaluated data libraries.The computer file includes evaluated neutron cross-section data for 206 (n, 2n), (n, p) and(n, a) reactions in the energy range from threshold to 20 MeV, leading to well specified radio-activities. The data are presented in the form of graphical plots and tables. An estimate of theaccuracy of the evaluated data is also given in the tables wherever possible. The file can beobtained on magnetic tape in the ENDF-V computer format upon request from the NuclearData Section of the IAEA.
1. INTRODUCTION
The present compilation of fast neutron induced activation reaction cross-sections, covering energies from threshold to 20 MeV, is based on evaluated datataken from different evaluated data libraries and individual evaluations. Themajority of these evaluations were prepared by using available experimental data
* Present address: Institute of Physics and Power Engineering, Obninsk, Union of SovietSocialist Republics.
305
306 MANOKHIN et al.
for selecting the parameters needed in theoretical computations and for normalizingthe results of such computations. Theoretical calculations were also used forthe interpolation and extrapolation of experimental cross-section data.
The significant progress achieved over the last ten years in the theoreticaldescription of these activation reactions must be emphasized, especially since theprevious edition of this Handbook [ 1 ] included only a compilation ofexperimental data. The reasons for this progress are (1) development of statisticaland pre-equilibrium decay models [2-4] and (2) a better understanding of nuclearlevel density problems [5].
2. PROCEDURE FOR FILE PREPARATION
The following libraries and individual files of evaluated neutron cross-sectiondata were used for the selection of the activation cross-sections: the BOSPORLibrary [6], the Activation File of the Evaluated Nuclear Data Library [7], theEvaluated Neutron Data File (ENDF/B-V) Activation File [8], the InternationalReactor Dosimetry File (IRDF-82) [9] and individual evaluations carried outunder various IAEA research contracts [ 10, 11 ]. All of the evaluated data curveswere compared with experimental data that have been reported over the last fouryears. Only those cross-sections not in contradiction with the latest experimentaldata were retained in the present activation data file. In cases of several conflictingevaluations, that evaluation was chosen which best corresponded to the experi-mental data. A few evaluated curves were renormalized in accordance with theresults of the latest precision measurements.
The file of selected reactions contains 206 evaluated cross-section curves ofthe (n, 2n), (n, p) and (n, a) reactions which lead to radioactive products and maybe used in many practical applications of neutron activation analysis. Somecompeting activation reactions, usually with low cross-section values, are givenfor completeness.
3. PRESENTATION OF THE DATA
A graphical form was chosen for the presentation of the data. The computercodes Linear and Evalplot [12] were used for plotting the figures. To providemore information, and to make it possible to use this Handbook for simpleestimates, tables of numerical values of the cross-sections, in neutron energy stepsof about 1 MeV, were added to the figures. Whenever possible, an estimate of theaccuracy of the evaluated curves is also given in the tables. If the accuracy of anevaluation is not given, it is supposed, in most cases, that the accuracy is ±30%or lower.
PART 2-3 307
The computer file of the cross-sections (plus the covariance matrices ofthe uncertainties in a few instances) for all compiled activation reactions in theENDF/B-V format is available from the Nuclear Data Section of the IAEA and maybe obtained upon request either on magnetic tape or in the form of listings. Thisfile contains more detailed information about the energy dependence of the cross-sections (a 100 keV energy mesh is normal) and some additional bibliographicinformation.
An attempt has been made to specify clearly the activity created by a givenreaction. In the case of the formation of an isomeric state, the term 'Isomericstate' is given in the figure. In the case of a cross-section for the independentformation of ground state activity of the residual nucleus (without populationthrough internal transitions from an isomeric state) the term 'Ground state' is used.No label on a figure means that the radioactive residual nucleus has no isomericstate. If it does have an isomeric state, then the sum of m + g is given only if it isequal to the cumulative cross-section of formation of ground state activity. Thiswill only be the case if the half-life of the isomeric state is much smaller than thehalf-life of the ground state, the branching ratio for the internal transition from theisomeric state is close to 1 and the cooling time for measurement of this activityis chosen which is much larger than the half-life of the isomeric state. Cumulativecross-sections of formation of ground state activity for activation analysis purposesshould therefore be used with great care.
4. RELATIONSHIPS WITH OTHER SECTIONS OF THIS HANDBOOK
Owing to limitations of space, it is not possible in this section to give moredetailed information on the decay properties of residual nuclei. It is assumed thatthis information can be taken from other chapters of this Handbook, or from otherpublications [13].
Regarding the degree of consistency with data presented in Part 2-2,it should be emphasized that the 14 MeV values from both sets agreed within thelimits of the estimated errors.
ACKNOWLEDGEMENTS
The authors are greatly indebted to the staff of the Nuclear Data Section,IAEA, for their help in the preparation of this chapter.
308 MANOKHIN et al.
REFERENCES
[ 1 ] INTERNATIONAL ATOMIC ENERGY AGENCY, Handbook on Nuclear ActivationCross-Sections, Technical Reports Series No. 156, IAEA, Vienna (1974).
[2] INTERNATIONAL ATOMIC ENERGY AGENCY, Nuclear Theory for Applications(Proc. Course Trieste, 1978), IAEA-SMR-43, IAEA, Vienna (1980).
[3] INTERNATIONAL ATOMIC ENERGY AGENCY, Nuclear Theory for Applications-1980(Proc. Interregional Advanced Training Course Trieste, 1980), IAEA-SMR-68/1, IAEA,Vienna (1981).
[4] INTERNATIONAL ATOMIC ENERGY AGENCY, Nuclear Theory for Applications-1982(Proc. Course Trieste, 1982) IAEA-SMR-93, IAEA, Vienna (1984).
[5] Basic and Applied Problems of Nuclear Level Densities (Proc. IAEA Advisory Group,Mtg. Upton, NY, 1983) (BHAT, M.R., Ed.), Rep. BNL-NCS-51694, BrookhavenNational Lab., Upton, NY (1983).
[6] BYCHKOV, V.M., MANOKHIN, V.N., PASHCHENKO, A.B., PLYASKIN, V.I., CrossSections for the (n, p), (n, a) and (n, 2n) Threshold Reactions, Rep. INDC(CCP) -146/LJ(1980);BYCHKOV, V.M., ZOLOTAREV, K.I., PASHCHENKO, A.B., PLYASKIN, V.I.,Establishment of the BOSPOR-80 Machine Library of Evaluated Threshold ReactionCross-Sections and its Testing by Means of Integral Experiments,Rep. INDC(CCP) - 183/L (1982), Nuclear Data Committee, IAEA, Vienna. (Englishtranslations from Yad. Konstanty 1 32(1979)27; 2 33(1979)51; 4 35(1979)21;3 42(1981)60.)
[7] The LLNL Neutron Activation Cross-Section Library of 1982, documented inRep. UCRL-50400, Vol. 18, 17 October 1978, Lawrence Livermore National Laboratory,Livermore, CA (1978).
[8] The ENDF/B-V Neutron Activation Cross Section Files, documented inRep. BNL-NCS-50496, Brookhaven National Laboratory, Upton, NY (1979).
[9] CULLEN, D.E., KOCHEROV, N., McLAUGHLIN, P.K., The International ReactorDosimetry File (IRDF-82) in Energy Dependent Form, Internal Rep. IAEA-NDS-48,IAEA, Vienna, 1982.
[10] ADAMSKI, L., HERMAN, M., MARCINKOWSKI, A., Evaluation of the cross-sectionsfor the 28Si(n, p)28Al and the 181Ta(n,2n)18(>ra reactions, Final Report, IAEA ResearchContract No. 2741/RB, 1983.
(11] IVASCU, M., AVRIGENAU, M., AVRIGENAU, V., Nuclear Model Calculations of(n, p) and (n, n'p) Reactions on Molybdenum Isotopes, NP-28-1983, Final Report,IAEA Research Contract No. 2983/RB, 1983.
[12] CULLEN, D.E., Program LINEAR (Version 78-1): Linearize Data in the Evaluated NuclearData File/Version B (ENDF/B) Format, Rep. UCRL-50400, Vol. 17, Part A, Rev. 1, 1978;Program EVALPLOT (Version 79-1): Plot Data in the Evaluated Nuclear Data File/Version B (ENDF/B) Format, Rep. UCRL-50400, Vol. 17, Part E, 1979, University ofCalifornia, Berkeley.
[13] Table of Isotopes, 7th edn (LEDERER, CM., SHIRLEY, V.S., Eds) Wiley, New York(1978).
PART 2-3
CROSS SECTIONS
309
3 - L I - S
1|nxMevT3ii8T47o6T51ooT6726T7iooT87o6T9iooTioioTii.oTi|7oII g.Bb T0.O0T35.0T3O7H21.oTl6.8Tu.7Tl3.5Tl2.3Tll7sTl0751
I EnlMevTll70n4i0Tl5.0116.0117.0118.0119.0120.01I "o,»b~T9. 7OT?7OOT873OT7.7OT7.5OT7.3OT7.06T67801
. 0.02
0 . 0 !
. 0.00
CROSS SECTIONS
ENDL/AI7] 0. 10
: o.o8
0.06
I En,M»Yl0.67T0.74Tl.3oTT750TOOI2.60l27goT3.55T4700T57oO II q,»b 10.00100217.OoTl6.ott57oT9S.oTl55.'fiO57T85.o1t5.Ol
I En1MevT7iOOT9;OOTl21on475T20.01ra.mb~T35.5T22.0Tl5.oTlO.5Ts70OI
HEV7 8 9 , n l
11 -BE-9
310 MANOKHIN et al.
CROSS SECTIONS 5-B -10
5-B-10(N,T)4-BE-8 .^2012TooT37ooTJ7o6T5Too16.ooT77ooT8T6oT97ooTio7pI •
I a.mb To.OoT2O.oT2876T62.5Tr35TTl5O.Tl47TTl3aTTl3lTTl25^
I EnJtevTuToTl2.5T1376114^oTl 5. 5Tl6. STl7^oTl8?gTl9^0120751I I I I i
6-C-12(N,P)5-B-12IEn7MevTl376Tl5?oTl6ToTr7ToTl8ToTl9?OT207oII ~ o x n b j 0 . 0 O T l T 5 0 T 7 . j 7 j r 7 T T 5 T T
Z T ~ 3 O . " J 7 " 2O. " T 100. I
q o. is
. 0. 10
0.04
0 . C 3
0.01
MHT 7 3 0
PART 2-3
CROSS SECTIONS
311
MRT 830
: o . o i o
. 0.008
4 0 . 0 0 6
0.004
7-N-14(N,2N)7-N-132,oli3. oTu7oTi5ToTi6ToTi 7ToTi87oTi 97oT2oTo I
5.9oTOoT9. sotioTTTioTsTio. 1T9T40130^ I 1
j 0 . 0 0 2
0.000
16
MEV
CROSS SECTIONS
7 - N - H i
8 - 0 - 1 6
IN, P!
6OSPOR 161
8-O-16(N,P)7-N-16En^MevUO.2111.0112.0
o nb |0.00|7.00|50.0A«,t 1 20.
13.032.0
14.0115.0116.0117.0118.0119.0120.045.5|37.3|32.O
10. 1 8.27.5124.5123.0122.0
20.
0.06
0.02
. 0.00
-To1-0 -16
312
MfIT 920
MANOKHIN et al.
CROSS S E C T I O N S 9-F -19
IRDF [91
9-F-19(N,2N)9-F-18
0.06
lEn,Mevlll.o|l2.oTl3.o'n47oTl5.oTl6.oTl77oTl87oTl97oT2o7ol 1 n n ,! ?!**!? .j°-20!6.09T2074T40.9T57.5T68.8T77.2f8378p3.5T83751 "• '
MEV
CROSS SECTIONS
9-F-19(N,P)8-O-19
I EnjHey 14?26T5755T67ooT7TooT87ooT97ooTio7oTiiToTi2T0T157oII "o.mb To7ooiT75oT20. oT327oT4o7oT43• 5T42.5T38.5T3375T27.51I Z£~l 457 T is? *
l"5,mb T22.5fl8.0Ti5.0Ti2.5Tll.0T9.60T8.001^ 2o
. o.ou
, 0 . C 3
0 . 0 0
MEV
MHT 9 3 0
PART 2-3
CHCSS S E C T I O N S 9-F
IN fi! PHC
BOSPOR 16]
-19
)
-i n
1
. 0.
1
?n
i s
313
J 0. 10
9-F-19(N,A)7-N-1611EnJ^iev11.60U.001 5 7 M T | 7 O O T 7 7 O 6 T 8 7 O O T 9 7 O O 7 I O 7 5 T I I 7 O T I 2 7 O I
I"o,ab~To7o5T48 • 5794. pTl947Tl377TlOO.T827oT6875T5|7oTJl7o I N12e£z__[_ 30. I ~~ ^9"~—~~T" ~-.l2i.
iTi37oTT47oTI|7oTi67oTi77oTI|7oTi|l2T2o7o]I "o^mb | 4 4 7 O T 3 6 . O T 3 1 . (^267072170118^0114^0113^0
375^4^157^16^071772718.^1978ll2li5iiIIIi2ll§iF"7iT8673T9874
. 0 . 0 6
J Q . C 2
j 0 . 0 0
MEV20
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314
MHT 1 1 3 0
MANOKHIN et al.
CROSS S E C T I O N S
ll-NA-23(N,P)10-NE-23
I En2fievT3T75T5T00T6T06T7T00T8T00T9T06T16T6T11T0TI2T6T13T01
I Z2x5feIl2l29lLl2liZIIIIll2liIl2ll I • IIUIIIIZIIII1IIII !I°11 |nIBIiTni9Tl57oTii7oTi7ToTi8ToTi?7oT267g II S^IIillili^oIlzoTglToTloToTiAITioo!
0.02
J 0.00
MEV
CROSS SECTIONS
II-NB-23
11 -Nfl-23
(N,flLPHP)
BOSPOR [61
U-NA-23(N,A)9-F-20
I|nIffiJT47o3T77ooTlTooT97o6TIo7oTiI7oTr276Ti37oTr47oTi 5751I _?i°b.To^.ooT7. 5oT327oT65.679875T130. Ti48TTi547Ti537Tl45711 ?il—I.. Z|o H _ i r n • IIIII-II_2o7~"~~TI~~"io7"""~ 1
1IsIsI5Ti67oTi77oTi87oTi97oT2o7o1I oimb_Tl247Tl637T827oT6l7oT4276Ii&?Ir~Illlllllliiiiiir 1
0. 15
0.05
. 0.00
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MPT 1 2 2 0
PART 2-3
CROSS SECTIONS
315
12-MC-24(N,P)ll-NA-241En7MevT479oT575oT67ooT776oT8766T97o6Tio7oTiI76Ti27oTi57oII ~;,Sb~TS7oiTo7o2TI79n5577TIo67Tu97Tu8.Tl587Ti827Ti9871l4LIZZIZZZZZZl2ZZZZZZIZZZZZZZZZZZ-ZZZZZZZZZZZZIZIZZIZ2iZl
I|n^MevTr47oTi576Ti675Ti77oTi87oTi97oT267o|I ;,ib"Tl977Tl787Tl407Tl227Tll4.T977IT977IIlAo.r~T~i.~l 4. "T 57 T~2o7|
0.20
0. IS
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MflT 1236
10MEV
CROSS SECTIONS
15 2012-MG-2U
12-MG-2S
0. 05
. 0 . 0 0
12-MG-25<N,Pni-NA-25I En2ffivT4757T4787T5747T|75oT775OT875OT975oTir7oTi375Tl57o I1 -?i55.i5i22liiI2i*Zn22l2l42l2'''487oT527oT|57oT557oT4o751
lEnJJevTl77oT2o76|I Zii.5iZIIli2ll2l21
0.05
0.03
0.02
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316
MflT 1235
MANOKHIN et al.
CROSS SECTIONS 12-MG-26
ENDL/A [7]
lEn^MevTs.reTsTilTioToTii.oTi.oTisToTis^onoTolI ~"*i»~~TO7OOT2786T357OT7~7OTB87OT887OT~0• Oi l5 • 51
0.08
0.04
(N,fllPHfl)
0.00— _
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CR05S SECTIONS
12-MG-26
13-3L-27
. 0 . 10
J 0.00
PART 2-3 317
MBT 1340 CROSS • 3 - R L - 2 7
MEV
ROSS S E C T I O N S
14-SI-28(N,P)13-AL-28
7 p o T 7 7 p o T 8 T o o T | 7 o o T I p p lo.OOl2O.5T84.6T23l7T2847T263TT2947T318.T356.T319. I
j j)\ lOTnToTIOTi 97oT2o7610,mb~T2837T229TT212.Tl637
|AO,Z"T"47"T 8 . 1 17. T"l3. I
4 0 . 1 2
j 0 . C 5
: 0 . C 2
MEV U - S I - 2 8
318 MANOKHIN et al.
CR35S SECTIONS
ENDL/AI7]
U-SI-30(N,A)12-MG-27T 7|TiI7oTIi71TO"iTiIl2Ti67ITl7lITilII!
i L l 7 J T j 7 J I E l l IllnTjievTwTiTloTolr<>,ob"T38.lT33.1l
J 0 . 0 8J
. 0 . 0 6
0 . 0 4
j 0 . 0 2
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-. 0.00
ItHEV
CROSS SECTIONS
IB 20
1 - S I - 3 0
I S - P - 3 1
'- 0.05
: o.oi
i 2 7 7 T i 3 7 o T l 4 7 o T n 7 o T 7 T 7 T T T l-To^OOTon5T87°5Tl675T24;_5T337oT4noT4775T52_. 51
T~ 507 T"25.T_~__Z_I_I 50; I
. 0.02
0 . 0 1
0.00
MflT i 5
PART 2-3
CROSS S E C T I O N S
319
MflT ! 5 3 O
|En,McvTi7561276613.061^.061570016.601770018^0019700115^01 'I "a,Bb'TI.10T9783T6675T8579Tl25.Tl427Tl337Tl397Tl397Tl43.1 ]
l4?lOIIlIIISIIIliIIII~II~II"~ZlIIII"IIII~-II-I I 1IEii7MevTIi7oTi275TI37oTi47oTI575TI675TI775TI§76Ti97oT|o7oIl"S,;b"TT387Tl227TiO7.191.911173174.3166^7166.215475149771IAS.Z ~T5rrr"T A . T J T T 57"T"87"T"ig7T ZYT iL__ I
5 6 7 8 9
MEY
CROSS S E C T I O N S
10'1S-P -31
I S - P - 3 !
IN.RLPHfl]
BOSPOR 161
15-P-31(N,A)13-AL-28I Ei2S7r27orr576oT67Mr7766T8To6T97goTio7oTii76Ti |76Ti3761I olmb_Tp_:00T3i00T23.0T55.6T85.6Tll77Tl357Tl4l7Tl397Ti307l
0. 12
0. 10
0 . 0 8
I EnTjievTUToTI sToTKToTI 77oTi876Ti 97oT2o761I" \ S b ~ n i 77Tio3j8776T7T76T5 775T4 37oT357o Il l o , ! ~T~ i57 T 557 I
15H C . O O
15-P -31
320
MflT ; 630
MANOKHIN et al.
CROSS SECTIONS 16-S -32
. 1.5
. l . C
/
/
16
16-S-32<N,2N)16-S-31
IEnJievTlS.6TI6.0Tl7.6Tl8.0Tl9.0T201"o^nb'To. 00T0T1IT0.66T1T16T1T51T1TlAo^Z T 30. T 50.
17 18 19
.0172|
1 •j
:
•
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0.5
MEV
CROSS SECTIONS
16-S -32
16-S -32
; <r,mb i4J2l:5B|'i328l!15i-i2i0iC 8 : Jl
. 0 . 4
J 0. 1
16-S -32
MfiT 1635
PART 2-3
CROSS SECTIONS
321
16-S -33
IN.PI
ENDL/A 17]
16-S-33(N,P)l5-P-32I Ei2Mi;TI700T2768T3728T47l8T5738T6728Tu77Ti276Tl276Tl4741
I l2i5iIIO9llOni2lIiIlI]il|7Il?IIIl99ini!IIlllin2?I II En7jievTl67oTl 7^671875119.0120^011'"••i~Ts575T»o. 0T2s75Ti87ofi3.0[
0.2
0. I
I En7EvT47 A5T77ooT87ooT97ooTio7oTiroTi2. oTn7oTl47oTi 1751! ILsiltoIo^ironZlpJSnoTlo^pJIz^pT? 070^0178^0168701
I Eg7ite^Ti67oTiroTr87oTi975T2o7o I! _2i.55ITlZIIin4liniIIiiiIIi92i I
0.08
0.06
0.0U
0.02
0.00
12 mMEV
18 20
16-S -3U
322
MBT 1610
MANOKHIN et al.
CROSS SECTIONS 1 6 - S - 3
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. 0.06
27-C0-59(N,P)26-FE-S9
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HBT 2850
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28 -N I -58
(N.2N)
IRDF [91
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28-111-58(11,2H)J8-BI-57
0 . C 6
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28-NI-58(N,P)27-CO-58-M
I ES"ffivT67S3T05n75oT3noT4r4oT5740T6T6oT77SoT8T56T9T5o |1 IiiiiZl2l2°l2i52ll2l2li2fIIl2lIIll2lin2lIIiiIIli2lIliII IIEn7SevTioT5TiiT5Ti27STi3T6Ti4T6Ti5ToTi67oTi8T5T2o7oII I»i.5iIIl2lIIi!2lIiIlIl2liI[i52lIiIlIIHl2lZlIoT75l21
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(N.P! IROF[9|
28 HI-58(H,P)27-0O-58-ll+O
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28-N1-58
28-NI -58
6.00T7.00TIT00T9.ooTioToTiiTolTl
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28-NI-60(K,P)27-CO-6O-M
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28-tJI-6O(N,P)27-CO-6O-M+G
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28-NI-64(N,P)27-CO-64
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28-NI-64(N,A)26-FE-61
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29-CU-63(N,2N)29-CU-62
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29-CU-SS
29-CU-65(N,A)27-CO-62-G
ToTi 275Ti IToTuToTI 57o ||76oT873oT?79oTiu5TiI711
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358
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3O-ar-64(S.F)29-CU-64
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30-ZN-64
30-ZN-66
30-ZN-66C N,2N)30-ZN-65
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3O-ZN-66(N,P)29-CU-66
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30-ZN-66
3O-ZN-68
• ooTTo75Tii7on3. oTu7oTi 3. oTi|7o |
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31-GA-69(N, 2N) 31-GA-68
i l2rSirTo7ootfo7ot55oTT635TTi657tl015Tlll5Tll25Tl220Tl2AfTl2S51 :,_i_5i_J 8^ |
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31-GR-69
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31-GA-69(N,P)3O-ZN-69-M
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31-GH-71
32-GE-70
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32-GE-70(N,P)31-GA-70
6709T6799T7759T87l9T9739Tl370Tl579Tl574|I Iiiili2l22ilIZ5npj5TJ?iiTn76T84i8T|2i4T|37gT87ig7||721
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IB 20
32-GE-70
32-GE-72
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32-GE-72(N,2N)32-GE-71
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32-GE-7U
32-GE-76
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32-GE-76(N,2N)32-GE-75-M+G
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32-CE-76(N,P)31-GA-76
2Ti 27iTi3T|Ti|T4Ti6722liII*iniiIlIliIli5oT|786T2Tj7Ti765Ti754
33-AS-75(N,2N)33-AS-74
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33-HS-75
33-HS-75
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33-AS-75(N,A)31-GA-72
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367
314-SE-74
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c.t
1 C.2
j G.O
m 16MEV
18 2037-RB-B7
PART 2-3
CROSS SECTIONS
371
1 1.5
_ | | T T !I oj»b T0.OOTl5.0T280.T836.Tl22gTl38gTl47gTl50oTl500Ti495l
J T 1 5 ~ ~ T ~ " ~ " " 10. I
. 0.0
MHT 38SD
MEV
CROSS SECTIONS
IN.P)
BOSPOR [6]
38-SR-86(N,P)37-RB-86-M+G
'I|n2MevTnooT67ooT77o6T8755T976oTio7oTii75Ti27oTi37oTi47oII aimb"To75oTo77oT27ooT57ooT97ooTi47oT2r75T2876T367oT427o IIAO.Z T 3o7 T 157 T"o71
0 . 0 3
O.OJ
0 .01
^ 0 . 0 0
"TT"
372
MRT 38140
MANOKHIN et al.
CROSS SECTIONS
BOSPOR |61
38-SR-88(N,2N)38-Sft-87-M
l|n^McvTii7|TiI77Ti27oTi37oTi47oTi576Ti67oTi77oTi87oTi97oT2o76lI <F mb'To7ooTl77oT447otl6o7T2857T33|7T364^T374iT3777T3687T3277[|£o % ~T~ 177 " T " 15. ' ~ ~ ~ ~ r~"l
0.3
[N.JNI ISOMERIC STRTE
]J_; 0 .1
j
I
0.0IB
MEV
CROSS SECTIONS
18 20
38-SR-88
(N.PI
BOSPOR [6]
0.03
0.02
0 .01
n2S5T5TTiiTi2oTi37oTi47oTi576Ti67oTi7l6Tr87oTi976T2o7ol<ji5b"To7ooT6.6oT2.ooT47o6T8.ooTi2.oTi87oT2376T27.oT|9.oT3i75T327o!J j - j ~ ~ 55T T"lI.T" 20. I
38-SR-6
PART 2-3
CROSS SECTIONS
373
39-r -89
(N.2N1
BOSPOR 16] 1.0
0.6
0.2
: o . o16
MEV
CROSS SECTIONS
1839
39
-T
-Y
20-89
-89
(N.P)
BOSPOR [61
39-Y-89(N,P)38-Y-89
2i?«Fo772T|7ooT77ooT|7ooT97ogTIo7oTii7oTi27oTi37oTi47ol
I E^Sj;Tl5:oTi|ToTi7ToTi8ToTl976T26T61Il2i3iITllI5T|s7oTl47gIlil2llll2lIll2I
fa fz iMEV 39-Y -89
0 . 0 2 S
0 . 0 1 5
0 . 0 1 0
0 .00S
0 . 0 0 0
374
MRT 4020
MANOKHIN et al.
CROSS SECTIONS
1N.2N!
IRDF[9]
MHT qO35 CROSS SECTIONS
(N , P]
ENDL/A |7I
W-ZR-90
1.0
o.s £
o.u
: o.o
HO-ZR-92
40-ZR-92(N,P)39-Y-92
I in2MevT|T5iT878iTio7oTiiT2Ti2TiTn76Ti4T|TIol91I i i I l Z l l i n i I l l l l l I l l l I l I
0.015
0.010
0.005
0.000
18 2D
UO-ZR-92
MRT 4035
PART 2-3
CROSS SECTIONS
375
4C-ZR-9I4
-
f1IH PI
ENDL/A171
•
; /
: /
i /- 1
/ :
I 40-ZR-94(N,P)39-Y-94
/ li5iMevT9.87TlO.2TlI.lTl2.3Tl3.2Tl4.ITl5.6Tl6.8T2O.01 •
-
'. 0.010
MPT 4120
16
MEV
(N.N-I CROSS SECTIONS
I SnjtaVj_12- 0 [ 18^.0^19.0 • 20 .0 J•,~f.mt '22.9.;2O.5'18.7il8.2;
: 5 r J C i T O " ~ " ;
J 0.008
: 0.006
18 2040-ZR-94
m-NB-93
IRDF [9]
0.2
J 0 . 0
MEV I-NB-93
376
MHT 4 1 3 0
MANOKHIN et al.
CROSS SECTIONS
. 0.1
: 0.3
41-NB-93(N,2N)41-NB-92-M
T9To4T9T2oTio7oT|noTII7oTr37oTr4ToTi57oTi676Ti7ToIlo,nbTo7o6T3.65T9475T3007T42o7T4667T483.T4777T4577T4267|
42i5_II L__1 iSilZI L1J"T "•I En7.MivTl87oTl97oT267o |I"5,nb"T39l7T3567T3187II S T "7. I
MEV
CROSS SECTIONS
42-MO-92(N,P)41-NB-92-M
I En2MevT575|T5786T67l6T77o6T'I''T97r|Tro7ITII73Tl272Tl37o I
I I i i l 2 2 2 l I ° 2 l l I i l I I 5 l I l l I I Z I I I I l I l I I I
IEn2SevTi475Tl57oTi67oTi77gTi876Tr976T|o7oIIii5iIII§IZl5878T4876T4077T3475T2976T24.31
. 0.06
. o.on
. 0.02
18 20
H2-M0-92
PART 2-3
CROSS SECTIONS
377
ENDL/AI71
42-MO-94(N,2N)42-MO-93-HH;
IEn2SevT9778Tlo73Tll74Tl27oTl37oTl478Tl779Tl975T2o7oIII?ii5IIol22l[og7T6Oo7T8|g7T9ogj95g7T95o7T85O1T75o7I
1N.2N)
0.1
11 16MEV
CROSS SECTIONS
18 50
142-M0-94
H2-M0-95
42-MO-95(N,P)4l-NB-95-M+<;
I52l^ivT67i5T776gT87;ogT97ogTio7oTii7sTill2Ti37oTi47oTr|iOI
Se;Ti67oTi776Ti87oTi97oT2o7oI
ilHilllSIIllilliliH
12 11
MEV
18 20
U2-M0-9S
378
MHT 1)260
MANOKHINetal.
CROSS SECTIONS
1 0 . 0 5
. 0.014
0.00
MEV
CROSS SECTIONS
IB 2012-M0-96
•42-M0-96
I |n2MevT274|T|7ooT77ogT§7g6T97o6Tig7oTii7oTii7oTn76Tr47g II i I l l l l l l 5 I I I l l 5 l Z I Z l I 5 I I I ? n 2 I
I injSevTI576Ti|76Ti77oTi876Ti975T2o7oI. 3Ti975Ti6T7Ti3. 8TI|7oTii721
. 0.020
. 0.010
. 0.005
142-M0-96
PART 2-3
CROSS SECTIONS
379
^^-M0-^7
( N , N " P ) Ivasculnl
42-MO-97(ti,N'P)'il-NB-96
lEnIJte;T932Tl37oTl4.6Tn7oTl67oTl77oTl8.oTl97oT207ol1 -?i5^-l2l22l2i25Tl1JoT47ooT7760Tl2;|Tl777T2373T29741
o.oso
o . o i s
0.005
. o.ooo16
MFU 14270
MEV
CROSS SECTIONS
18 20U2-MO-97
I N . P ) Ivascu 1111
42-MO-97(N,P)41-NB-97
IEn2MevTiTi6T7702Ti7ooT97ooTio7oTii7oTi275Ti37oTi4"5Ti57o I
I i I o I o o I i l I f T ^ T ^ r T r i r J g T T i r o T i l 751
IEn^5evTl676Tl77oTl87oTl97oT2o76II IL5SlIiIIIIi2l6Tio7oT976oT97|g I
0.012
0.008
. 0.00M
o.oos
6 7 8 9 ]O1o.ooo
MEV1O1 2
U2-M0-97
380
MflT 4280
MANOKHINetal.
CROSS SECTIONS
Lrz
C N . N ' P ] Ivaseu [11]
42-MO-98(l»,K'P)41-!IB-97
IIn2MevT9789Ti4roTi5T6Ti6ToTi776Ti§7oTi9ToT26ToI1_HiiI_l2l°2l°IifeI°I§°IiIllIlIill5lliT8To5Ti575I
'.1 16MEV
: o .o io
- 0.00018 20
U2-M0-98
MflT M335 CROSS SECTIONS0.025
IN.P)
ENDL/AI7]
- 0.020
J 0 . 0 1 5
43-TC-99(N,P)«-MO-99
I En7ScvT375 7T3787T57o7T6727T77r7Tr27oTl279Tl474Tl576Tr678T267o I 1I I§i.iiIl2i22l2lznilIll2OIliIZIl5l2lllIin?IlinilIilI^niIl I
0.0C5
0.000
MEV
PART 2-3
CROSS SECTIONS
381
«-TC-99
ENDL/A [71
43-TC-99(N,A)41-NB-96
vT7754T77||T8TI|T874|Tf7oJTio7oTu71TJoToI
Q " l O l l I l l l I I 2 I I l l i I l
MHT M52O
mMEV
IN.N' I CROSS SECTIONS
. 3 9 . 7 5 KEV ISOMERIC STRTE
IRDF |9l
0.006
. 0.004
. 0.002
J
!N.fllPHfl)
18 2043-TC-99
1S-RH-103
45-HH-lO3(N,H' )45-»H-103-M
;&i.MoV'o.2o;o.4o:i.oo;2.oo!IjTjjS i^.iiTai.iSlSiiSoi. j
!BiTiiV7X3725!j.z5l5T25! 5ol77oo;f.5oX9looi~<rjJS iio3l!ioi6iiio2.;liliiii4i;ni5i.io94.:\K<r.iT \ ~ i l _ i ~ _5~ ~ I ~ i l
O.E
o.s
: o.i
0 .2
9
10" s rrxMEV 45-RH-103
382 MANOKHIN et al.
CROSS SECTIONS •17-HG-107
IN.f l lPHfl] [SOMERIC STfiTE ENDL/A 17)
47-AG-107(N,A)45-RH-104-M
I|n2MevT57|6T776oTig7oTi57oT|g7o II -°i5*-l2-°9l°ll2l5i22lill°"li57o I
"3 0.015
_ 0.010
_j o.oos
12 14
MHT M730
MEV
CR05S SECTIONS
18 20
L|7 -PG-107
47-RG-109
J 0.000
. 0 . 0 1 5
0.00547-AG-109(N,P)46-PD-109-M+G
,eT36T7.5oT87o6T97ooTro7oTii76Ti2.oTi37oTi47oTl57oIc^;b"To7ooTo76oTi7ooT272oT476oT6.0oTis7ooTn76Ti3.otxsTo I
i 5 l I I I I I I I l 3 ° I Z I Z I I " I I I ~ I l I ~ I I I ~ 7 ~ I
IEn^SevTi67oTi77oTi87oTri7oT2o7oIT o mb'Tl574Tl578Tl579Tl5.6Tl57o|
MEV18 20
47-BG-109
PART 2-3
Cf iOSS S E C T I O N S
383
(N.BLPKfi) GROUND STflTE ENDL/AI7]
47-AG-109(N,A)45-RH-106-C
IEn][MevT575gT97ggTio72TiiT2Tl27oTl3T5Ti57oT2o7oI'I?i5iIl2l22l2i2iI4~i8T574iT6758T97i6Ti27|Ti57oI
MHT 61437 IN.N' i CROSS SECTIONS
ii7 - B G - i 0 3
" """" 73 0 . 0 1 S
. 0.00018 20
H7-HG-109
4 9 - I N - i 1 5
. 0.3
. 0.2
,BiJiiVvi7ipo!l.opj.io.o;To78iii.i:i.3T5!i4.3',2o.o;Ijr^rt iJOTi! 2?l.iZ47i! 205.J.115. ',li~O162.0 [54.0''Ld? I _ _ I2 _ I 14 ! 22~ ~ ;
\ 0 . 0
8 9I00 3 1 5 6 7 8 9 , n l
1 9 - I N - l 15
384 MANOKHINetal.
CROSS SECTIONS
BOSPOR (61
49-In-115(N,2N)49-IN-114-M
IEn2ScvT973oT975oTi67oTiI7oTi27oTi37oTi47oTi575Ti67gTi77oI"gimb"T0766Tl07oTl5o7T5707T8867Tl095Tl20OTl245Tl270Tl2751
TIIiIIIIIIIllIIIIIIIIIIIIIIIIIIIIIIIIII i! |^5evTl875Ti9"6T2o7g II OjOb Tl255Tll95TlO80li S r T " 157 ~ I
• 1 . 0
: 0 . 8
0.6 m
0.2
I N . 2 N I I S O M E R I C S T B T E
0.0
MflT 4940
MEV
CROSS SECTIONS
20U9-IN-1 15
W-IN-! 15
49-IN-115(N,2N)49-IN-114-M+G
IEn25evT|7iiT974gTio7oTii7oTi27oTi37oTi47oTi5loTi67oTi77oII"ai;b"Tg7ooTl275T2757T75O7tll8oTl48OTl66OTl75OTl80ofl825I'" "" " " ' r~T 157I4a.z._l 22i__L
! En"5evTl8. 0Tl975T20701• S " T p T T i
1.0
18 20
1 9 - I N - I I S
MHT 5030
PART 2-3
CROSS SECTIONS
(N.2N1
BOSPOR [6]
50-SN-112(N,2N)50-SN-lll
IEn^MevTig79Tii73Ti27oTr37oTi47oTi57gIi67gTiz76Ti87gTi9l2l?9l9I0Oj5O76T38O.T8
20. T"l57T _ ~_10.
1.2
0.2
MBT 5 1 40
16
MEV
CROSS SECTIONS
50-SN-112
5 1 - S B - l
51-SB-123CN,2N)51-SB-122-M+G
!En7MevT97o4T9.46Tro7oTii7oTfi7oTi37oTi476Ti57oTi67oTl77ol n H
rq.;b"T67o6T257oT28O7T72O7TIO4OTi256Ti384Ti44§Tl472Tl464| i
0.0
MEVIB 20
5 1 - S 8 - 1 2 3
385
386 MANOKHIN et al.
CROSS S E C T I O N S S 3 - I - 1 2 7
^Si^i^^iT^^oTio.oTiiToTinoTis^oTu.oTis.oTu.oTizToll_aimb ToTo6T3oToT2|oTTp0TTl20oTi41oTi52OTl575Tl590Tl59O|l A i "T is . T _ioT T 6.T ~ i o ~ " ~ I
J i .0
^MeTiiloTiloTJg|^mb Tl540jl360Tl200l
III~LL~
MHT 5S30
MEV
CROSS SECTIONS
18 SO
S 3 - I - 1 2 7
S 5 - C S - 1 3 3
55-CS-133(N,2N)55-CS-132
lInxMevT97o5T9.7oTig7oTri7oTI|7oll3.Oll4.Oll.5T0ll6.Oll77olralnb"T0.5oT5o70T2107T7607Tll75Tl45oTr586Tl60OTl520Tl340l
T 157 T" ~ to7 T"57"T
lEniMevTl8.0Tl9.0T20^0lO,mb"Tll36T9767T810"
lAaz T io7 I
0.0
PART 2-3
CROSS SECTIONS
387
S8-CE-1H0
I EnTSevTio. 0T10 J J i i i O T n i o T i S o T u T i s g T L Q T l Q T J i |!"ckinb"ToT0oTlO.oT32O.T66oTT850TT94oTT97O.T94O.T866.T75g7|
SJlII~IIIIilI~~II~ilIIIIiIIIII~I~~iIII'lEn7,MevTl97oT267o!I Oiib'TSooTTSsoTi
v i n is." ~_\
o.u
IN .2N1 ISOMERIC STRTE
0.04 16
MEV
CROSS SECTIONS
18 20
58-CE-1U0
se-CE-mo
(N.2N1
BOSPOR (61
58-CE-14O(N,2N)58-CE-139-H+C
I En2Se»T|727T9T4oTio7oTIIToTi276Tl3loTi4ToTl5ToTi67oTi7761I ^ imrTo7o6720.OT4357T9207Tl28OTl540Tl71oTl750Tl820Tl8151
i £!IIII__IiL_HIII IIIioIIIIIIIZLiilllllZZIIill 11I|n2>tevTl876Tl9"0T2670II Omb"Tl760Tl6l5Tl440|\ i j "T 77 I
1.0
0.5
. 0.0
MEV18 20
58-CE-1U0
388
MflT 5840
MANOKHIN et al.
CROSS SECTIONS 58-CE-112
BOSPOR [61
58-CE-142(N,2N)58-CE-141
TJlTSToOo.mb IO.OOT5007
T 10^ I 7.
I EnTSUTnioTilloTilloTioTo |' a.mb Tl360Tll20T910.T7O0.|
59-PR-141(N,2N)59-PR-140
IEn2MevT9746T977oTio76Trr7oTi27oTi37oTi47oTri7oTi67oTi77oIra,mb"To7o0T45.0T2607T8707Ti250Tl470Tmotr7O0Tr750Tl795l
lAa5.IIII~IIi51.I.Iiri..io7~TI._._.. .. .^
?Ist-Tl79gTl685Tl4751
1.5
0.5
. 0.0
. 1.0
D.S
MEV
MBT 6030
PART 2-3
CROSS SECTIONS
389
60-ND-112
MHT 6050
i i i i i i S Z f I . 1 . 0
60-ND-142(N, 2N)60-ND-141-M+C
I |nifievT9788TIo7niroTi27oTl376Ti476Tl57oTi67oTi77oTp7o Ib~T0766T29.2T3757T935.Tl385Tl630Tl760Tl825Tl870Tl892l
"IliOi-IIIZIIIIIIZIIIIIIIIIIi'
1 En7H=vTl976T2O7o I1854TI7O5I
\2e,z "T 107
. 0 . 5
MEV
CROSS SECTIONS
JOSO-ND-112
60-ND-118
BOSPOR 161
6O-ND-148(N,2N)6O-ffl)-147
I ES7Mevl7.37l7.70T8.00l9.00ll57olll.Oll2.0in7oTi47oTn7o I1 Sl2l22li2l2llZ2l22liS2SinilIiillIi5?2liZ2oil5221
1 -?ia7oril7oTi |7oT2o7o In l l I l l I
l . S
1.0
. 0 .0
MEV!8 20
60-N0-1U8
390MRT 6060
MANOKHIN et al.
CROSS SECTIONS 60-N0-150
BOSPOR 161
60-ND-150(N,2N)60-ND-149
I EniMj;T774iT87ggTfTooTio7oTuT5Ti27oTn7oTu7oTi57oTi67o I1 i i I I i I i 2 i l 8 8 0 Jl27OTl5O5ll66|Tl 725Tl740Tl69gTl|l01
I Ii>IS>vTi7loTi 876Tl97oT2g7o I5 Z I l i l I i i I I
0.5
_; o.o12 14
MEV18 20
60-ND-1S0
CROSS SECTIONS
62-SM-144(N,2N)62-SM-143-tt«;
I |SiMcvTl0. 6Tll7oTl27bTl i10Tl4 ibTl5. OTI6. oTl 7.511875119^0120.01I a.mb To75oT5O.0T65O.TlO85Tl4OoTl56oTl655Tl74oTl8OoTl84Oll86O
. 1.5
MEV
1HT 6260
PART 2-3
CROSS SECTIONS
391
65-SM-152
18 2062-SM-152
1R7 6J70 CROSS SECTIONS
BOSPOR [61
62-SM-154(N,211)62-SM-153
^ToTi 37oTi!ToTi IT0T16T01I!lIlnilil]lIIl
18 2062-SM-1SU
392
HflT 6735
MHT 6735
MANOKHIN et al.
CROSS SECTIONS
ENDL/A (71
67-HO-165(N,2N)67-HO-164-M
TTIT874§T97o8T|7f8Tio7|TiiT8Ti|77Ti4l5Ti|74Ti6To Ii22l lL2l2*Ll623lI l58 Jj;O3|Tl049Tl050TiOO3T||871
I EnTjte vTl772Tl87lTT 975T2O761IIIIII*25TI*IiiI*2 371
(N.2NI ISOMERIC STRTE
0.6
H 0.0
mMEV
CROSS SECTIONS
18 50
67-H0-165
67-H0-165
67-HO-165(N,2N)67-HO-164-G
7iTu7oTii79Ti476Ti575TI 77oTi 5751
. O.£
- 0.2
GROUND STflTEJ j 0 0
18 2067-H0-165
MHT 6930
PART 2-3
CROSS SECTIONS
393
2.0
MfiT 7 1 3 5
. 1 . 5
. 0.5
- 0.0
MEV
CROSS SECTIONS
18 20
69-TM-169
71-LU-175
ENOL/A 171
10.plll.oTl2.0ll3.oTl4.oTl57oTl67oI4ir7T478.T5187T5427T5547T562.T533.I
(N.2NI ISOMERIC STflTE
O.H
0.3
0 . 5
0. 1
0.0
II
MEV
18 20
71-LU-175
394
MHT 7135
MANOKHIN et al.
CROSS SECTIONS 71-LU-17S
ENDUA171
71-LU-175(N,2N)71-LU-174-C1 lslMivT777oT7T8oT|TooT9TooTioToTiiToTi2ToTi3ToTIZToTI|ToII ^mbToiOoTl27oT2|ioT614TT999TJll'5Tl22lTl222Tri98Tll631
vliiToTiTToTiiToTiiToTioToiO.mb flO75T92l7T69O?T5l57T379. I
L:GROUND STflTE
1.2
1.0
0.E
0.S
0 .0
MHT 713S
MEV
CROSS 5ECTI0.NS
71-LU-175
71-LU-17S
(N.3N) ISOMERIC STflTE
ENOL/A171O.S
71-LU-176(N,3N)71-LU-X74-M
1lsIyiiTi472Ti474Ti57oTri79Ti77iTi87oTiiIIT2o7gII a,mb T6.00Tl.10Tl875Tlll7T4127T499.T547.T555.I
J 0.3
\o.
0. 1
0.0
MEV20
71-LU-176
MRT 7 1 36
(N .3N)
-GROUND STflTE
PART 2-3
CROSS SECTIONS 7 1 - L U - 1 7 S
ENDL/A |71
71-LU-176CN,3N)7I-LU-I74-G
IEnTjie vTi47oTi472Ti57oTi57|Ti77iTi87oTi972TIo7o Irg.mb"To.o6Tl7o5T257oTl29.T4127T4997T547.T5557l
17
MEV
CROSS SECTIONS
0 . 3
0.2
2
7 1 - L U - 1 7 6
7 2 - H F - 1 7 9
I N . P I
ENDL/A (71
395
0.003
72-HF-179(N,P)71-LU-179
I En7.MevTio7oTi 573TIo79Tl27iTi3. oTi379Tn7iTi67oTi772Tl87i II oimb"To.OoT6704To734Tl747T2.27T2. 78T5.06T37HT371413.141
|5;iMevTl9"7oT2O.6l
. 0.002
0 .001
. 0.000
MEV
20
72-HF-179
396 MANOKHINetal.
CROSS SECTIONS 72-HF-1B0
MRT 7330
2.0
• 1.5
72-HF-180(N,P)71-LU-180
"o^mb"to.Oofo.03to.5ofl.27fl.97f2.50T2.65t2.7ot2.7lT2.72|
j 0.5
16
MEV
CROSS SECTIONS
18 2072-HF-180
73-TH-18I
Adamski et al. [10]
73-TA-181(N,2N)73-TA-18O-M
I En2MevT7768T872lT972 5TIo73Tu73Tl2T3Tl373TIOTl673Tl873T20761I "o mb'To. O0Ti776T7187TlO85Tl322Tl37|Il352Ti28OTlO62T5O37T36571|/ya z "T 57 _ "T ' 77 LJ7^T I"|7~"J i37l
1.0
0.8
: 0 . 4
1 0 . 2
I N . 2 N I I S O M E R I C S T f l T E
\T mMEV
18 2073-TR-181
MfiT 7330
PART 2-3
CROSS SECTIONS
397
EK:M;vToT24Tio:iTn:oTi2:on3:oTi4ToriroTi6ToTi 7:6Tis:g iro,mb"To7ooTo7o4To.50117151271513.6011^2516^7017.8018.601 -l&uT~T 357 TSo.T io7 '__ _ ~ I 257 _ I
lEn,MevTl970T2070ll"a,;rT9725T9775l1 5 » . ~ T 207 I
4 IBMEV
CROSS SECTIONS
73-TR-181
0.006
O.OOM
0 . 0 0 2
18 2"0
73-TR-]81
ENDL/A[7I
74-W-180(N,2N)74-W-179-M+C
I En^MevT|766T878oT97i6TIo7oTiI76Ti47oTi67oTi77oTi87oT2o7611 1i i I l279n^I i227I i IooT90oT2iooTifooTi45oTi 200T10001
1 .0
Jo.:
/
t-'10 12 14 is 18
[N.2N1 1 .i -
2C711-H -180
398
MHT 7136
MANOKHIN et al.
CROSS SECTIONS 714-W - 1 8 2
IEnjMevTl7^0119. 0120^01
I I§L?On22ll222li22l I
MEV
CROSS SECTIONS
18 2 0
714-W - 1 8 2
CN.N"P) ENDL/A [71
74-W-183(N,N'P)73-TA-182-G+Ml+M2
0.008
o.ooy
. 0.002
MRT 71437
PART 2-3
CROSS SECTIONS
399
J 0 . 0 1 2
J 0 . 0 0 2
j 0 . 0 0 0
URT 71438
M£V
CROSS SECTIONS
(N.P1
0 . 0 1 0
0.008
0.002
0.00018 20
74-H -184
400 MANOKHIN et al.
CROSS SECTIONS
I En1MevTll^0TllT2Tl2. Ojl3.0Tl4.0Tl5. 0jl6.5TT675T18.5119^3120.01
16
MEV
CROSS SECTIONS
0 . 0 0 2
20714-W -181
18 20
7U-W -186
MHT 71439
PART 2-3
CROSS SECTIONS
401
7 1 - H - 1 8 6
ENDUAI7)
74-W-186(N,P)73-TA-186
I ESTSvTiriTriTsTnTiTnTSnsToTiSTnnToTiroTIoTo II I»IsiIIoI5ol9l2ll2ll?IiIi?Ill2ll5iIIIZll«IikiIi*ZI I
0 . 0 1 2
0.010
0.008
0.006
0.002
KHT 7139
16
MEV
CROSS SECTIONS
18 207U-W -186
-186
(N.flLPHfil ENDL/A17]
74-w-186(N,A)72-HF-183
I |nl«e vTII~oTii"2Ti27oTi37oTr4ToTi5ToTi|ToTi675Ti875Ti9T3T2oTo1
0.012
0 . 0 1 0
0.008
0.006
0.00M
0.002
. 0.000
MEVIS 20
74-W -186
402
MflT 7S35
MANOKHIN et al.
CROSS SECTIONS 7S-RE-13S
18 2075-RE-185
CROSS SECTIONS
. 1 . 0
18 207S-RE-185
PART 2-3
CROSS SECTIONS
403
7 9 - H U - 1 9 7
79-AU-197(N,2N)79-AU-196-Ml
IE;"MevT8776T97§oTii7oTl27oTn76Ti47oTr57oTi67oT2o7oI1 Iii»5IT2-°°Ii°-'°'''39^oT7o7oTioo7Ti267Ti4o^Ti.4o1Ti2o^ I
0. 10
o.os
0.06
0.00
2.0
l .S
1.0
0.5
0.0
79-BU-197
404
MBT 8035
IN .P )
ENDL/A [71
MRT 8036
MANOKHIN et al.
CROSS SECTIONS 80-HG-202
2 |1 -?i5i-l2i°°l2i°2lUl§l2l3lIii2ll2l
q 0.003
0.002
. 0.000
16MEV
CROSS SECTIONS
20
80-HG-202
[ N . 2 N ]
ENDL/A 17)
. 2.0
12 nrMEV
-tr
1.0 m
0.5
0.0
MRT 6036
PART 2-3
CROSS SECTIONS
405
80-HC-204 (N, t) 79-AU-204
I En7MevTl379Tl472Tl574Tl67oTl772Tl877Tl973T2O7o I 0 . 0 0 2
0.001
0.000
MfiT 8036
MEV
CROSS SECTIONS
20
80-HG-2014
80-HG-20H
. 0.002
. 0.001
0.000
20
80-HG-2Q4
406 MANOKHIN et al.
CROSS SECTIONS
81-TL-2O3(N,2N)81-TL-202
I En"MivT77zlT8766T97o6Tio7oTIi7oTl276Ti37oTi47oTni2TiS761\~a.mb To.OoT476ST35l7T9587Tl439Tl728Tr5l0T2017T2O80T2O24|
~I_U.7.~TI En JMcvTl77gTll76Tl97oT267o IIZ€i?iITi892Ti6|oTi37ITiigoIIAO.J; T" " "10." "I
MHT 8135
. 0.5
1 0.0
MEV
CROSS SECTIONS
18 20
SI -TL-203
81-TL-203
ENDL/AI7I
0.003
81-Tl-2O3(N,P)8O-HG-2O3
lEn~McvTi67oTio73TIo79Tr27iTi37oTi574Ti67oTI|79Ti87iTr973T267olI "o,mb"To7ooto7l2To799T3723T3799T4720T4.15T3.65T2774T2.25T2716 [
0.002
0.000
20
8 ! -TL -203
HPT 6 1 4 0
PART 2-3
CROSS SECTIONS
407
lEniMevT~58T8.2OT9.OOTlO;oTll.oTl2_10Tl3.oTl3i0Tl5ToTl6TolI lo^siZToTooT^oToTlTO Jll8oTl|7oTl810Tl940T2O0oT2O00tl9501
IAO^J is..I__i ZZ12ZZZZZZ Z iI En^Kvll IToTiiToTI 97oT2o7o II"atobZTl860Tl730Tl520Tl220lIflo.z" T i o 7 ~ "I
2.0
1.5
1.0
0.5
14
MEV
18 2081-TL-2O5
"HT 8 1 3 6 CROSS SECTIONS 31-Tl-205
81-TL-205(N,P)80-HG-205
I |57JpTn7oTu73Tii79Ti37iTiirjTi STiTnToTilTinoTg II <,,ub"To7ooTo766To745Tl. 46Tl. 85TI. 9OTl.i82TLi6Tl.iO51
o.s
0.018 20
81-TL-205
408
MHT 8230
MANOKHIN et al.
CROSS SECTIONS 82-PB-20I4
BOSPOR [6]
82-PB-204(N,2H)82-PB-2O3-M1+M2+C
vI !L44T9.ggTigToTii7ori27oTi3 • oTi* • oTiFToTi 67oTT 7?o Il Q^OoT487oT696TTl2721168oTl920T2064T2130T2148T20761
2.0
1.5
1.0
0.5
. 0.0
HHT 8235
MEV
CROSS SECTIONS
18 2082-PB-201J
82-PB-20M
( N . P )
ENDL/A |7]
82-PB-2O4(N,P)81-TL-204
I EoTfievTiOTio. 'TnToTi^s 1 1 | a I uT5Ti6.71 i776Ti974T2o7oII r?i»fc~l'°-0°T°"°^'0-23'l'l-95T2.54T3.l6T3.32T3.15T2T26T2.021
0.003
0.002
0.001
. 0.000
MEV20
82-PB-20H
HflT 6237
ENDL/A [71
MBT 8240
PART 2-3
CROSS SECTIONS
409
82-PB-2O7 (N, P)81-IL-207->»G
I|i7je7Tii7pTiI73Tl27JTl3TiTi4T5Tl7r3Ti8r2T5oT6|I5tJ°OoTo^JJ7jS2Tn5ni J[HO2liIiiIiI°4' I
IN. P)
16
MEV
CROSS SECTIONS
1.0
20
82-PB-207
82-P8-208
82-PB-208(N,2N)82-PB-207-M
IEn7SevT976oT97ooTio75TIi7oTl27oTI|7oT1475TI575Ti57oTI775I' o1«*"to7ooT25iiT2|o7T54o7T|4o7TiiooTi2l2lil22lil22n2*9!
I En7.MevTl87oTl?76T2O761I "a,mb~Tl15oTlO3oT88O71l i i . z "T 157 I
. 1.2
: i . o
. 0.8
. 0.6
. o . u
. 0.2
MEV18 50
82-P8-208
410
MHT 8330
MANOKHIN et al.
CROSS SECTIONS 83-81-209
. 2.0
83-BI-2O9(N, 2N)83-BI-208
I"o7Bb"To7ooT507oT9757Tl510Tl866T2l6oT2206T2250T2260T2222I
MBT 833S
MEV
CROSS SECTIONS
(N.P) ENDL/A(7I
83-BI-209(N,P)82-PB-209
I lilMe?T|7|oTii7oTiI7oTi3loTi47oTi|7oTiIIoTin<>TiE°Tii7pT|o7o I
2.5
0.0
8 3 - B I - 2 0 9
MBT 9030
PART 2-3
CROSS SECTIONS 9C-TH-232
[N.2N1
BOSPOR (61
90-TH-232(N,2N)9O-TH-231
I En3ivT6746T671oT77o6T87OTT97ooTio7oTn7oTi 27oTi57oTi47o ITO.OOTSO.0T5767Tl27bTl676Tl780Ti860Ti79oTl690Tl450IT „—T ~-:---^io7:~::::;;::~::r47ii
I En^MevTisTbTiOTi 77oTi87oTl975T267o 1I "oJmb_Tl076T700. T5307T4067T300. T23671
l4iJ*-HI~~I_IIiiII~~~II--~ I
MHT 9230
MEV
CROSS SECTIONS
IB 20
90-TH-232
92-U -238
( N . 2 N )
BOSPOR 161
92-U-238CN,2N)92-U-237
I |^ifevTinn|73oTno^T87OTTFMTio7JTn7oTi27oTl37oTu7o II »,nb"T0.OoTlo7oT5057Tl670Tl3l6Tl40oTl420Tl39oTl240T92o7I
i iCE:n~ii2ii~:iix~:~":iii;:~i:~nii i7 1
I£n7SivTr57oTr67oTr77oTi87oTI57oT2o7oIrS.Sb T61O7T46O7T36O7T29O.T2567T21O7|IA^'T Io7 I
O.£
o.u
0.2
MEV18 20
92-U -238
411
2-4. CALIFORNIUM-252 SPECTRUM AVERAGEDNEUTRON CROSS-SECTIONS
W. MANNHARTPhysikalisch-Technische Bundesanstalt,Braunschweig,Federal Republic of Germany
Abstract
CALIFORNIUM-252 SPECTRUM AVERAGED NEUTRON CROSS-SECTIONS.The status of the available experimental data on spectrum averaged cross-section measure-
ments for the neutron benchmark field of 2S2Cf spontaneous fission is reviewed. Particularattention is paid to the uncertainties of the experimental data, in the form of complete covari-ance matrices describing the interdependence of the data on the measurement procedure.Based on this information, a set of recommended data have been derived by generalized leastsquares techniques. The results from calculations of spectrum averaged data, based mainly onEvaluated Neutron Data File (ENDF/B-V) neutron cross-sections, are also given.
1. INTRODUCTION
The use of neutron monitor reactions in power reactors during routine opera-tion for purposes of neutron fluence and flux density determination requires priorestablishment of the measuring techniques and of the reliability of the nuclear data.This can best be carried out using certain neutron benchmark fields which havethe advantage of being relatively simple in structure. Thus, the benchmark fieldsof 235U and 252Cf are quite useful. Even if the field of neutron-induced fissionfor 23SU is more application oriented, owing to the fact that most technical neutronfields are driven by this fission source, the realization of a pure 23SU neutron fieldis hampered by spectrum perturbation effects arising from the epithermal neutronbackground, from wall returns and from scattering effects. This inherent disadvan-tage of a 235U neutron field can be circumvented by using the neutron field of252Cf spontaneous fission. With a compact form of a californium source and ahigh specific neutron yield (2.3 X lO'-s'^mg"1), neutron fields can be realizedwhich are almost free of spectrum distortion effects. The precision attainablein a neutron cross-section measurement in such a field is limited only by theuncertainties of the neutron-source strength determination (about 1%) and theactivation-detector calibration (about 1.5%). Assuming negligible contributionsfrom counting statistics, relative overall uncertainties of the order of 2% can beachieved. This makes 2s2Cf spectrum averaged data very useful for the valida-tion of energy-dependent cross-section evaluations. Owing to their high accuracy.
413
414 MANNHART
2S2Cf spectrum averaged cross-sections can also be applied to variance reductionmethods [ 1 ] with the aim of making possible more precise predictions of radiationdamage in reactor pressure vessels.
2. BASIS OF THE EXPERIMENTAL DATA
Since the last review (that surveyed the status of data available up to 1979[2]), the quantity of data has almost doubled. The data are indicated by thelabel 'Experiment' in column 2 of Table I. Columns 4 and 5 give examples ofrelated experiments: the reference reaction and the spectrum averaged cross-section value, <a>R, used for this reaction are shown. In addition, a brief descrip-tion is given of each experiment. It is also shown that some experiments havebeen superseded by more recent data and that some of the data have been revised.The experiments form two groups: those with a complete uncertainty descriptionand those with incomplete details of the experimental uncertainties. The formergroup of experiments is of particular importance, owing to their suitability foran evaluation of a recommended best set of data, as shown in Sec. 4.
2.1. Experiments with incomplete uncertainty information
The goal of attaining precision in determining spectrum averaged neutroncross-sections can only be justified if a detailed list of uncertainty contributionsis available which makes the information given as trustworthy as possible. Unfor-tunately, this aspect has been neglected in some experiments, which give onlyoverall uncertainties without specifications. It is most difficult to estimate thequality of this data and this further hampers their use for purposes of evaluation.
2.1.1. Experiment by Pauw and A ten [32 ]
The experiment is based on a neutron-source strength determination in amanganese bath and is therefore labelled in column 4 of Table I as 'Absolute'.No further details of the experiment and the activity measurement procedureare given.
2.7.2. Experiment by Kirouac et al. [11]
All data were measured relative either to the 54Fe(n, p) or to the s8Ni(n, p)reactions used for neutron flux density monitoring. The cross-sectionsused for these reactions were 87 and 105 mb, respectively. Unfortunately, theinformation given does not state which of the monitors was used for a specificreaction. While the monitor cross-section of 54Fe(n, p) is relatively consistentwith more recent data, the same is not true of the value of 105 mb used for the58Ni(n, p) reaction.
Text com. on p. 422.
PART 2-4 415
TABLE I. Cf-252 SPECTRUM AVERAGED NEUTRON CROSS-SECTIONS
Type of data Reference
React ion
r-19(n,2n) Experiment (1.08 ^ 0.16)xl0~
(1.63 . 0.05)xl0~
In-115(n,n') 199.4
Ni-58(n,p) 118.0
1977
1982
131
HI
Na-23(n,T)
S-32(n,p)
Calculated
Experiment
CaIculaled
Exp. r i .en t
CaIculatcd
Calculated
Recommended
Calculated
Experiment
Calculated
( 1 . 628.0 .054)x l0 *
( 1 . 6 2 6 . 0 . 0 4 3 ) x l 0 " 2
0.335. 0.015
0.2712
1.94 . 0.092.01 • 0.06
2.159. 0.088
5.11 • 0.434.89 * 0.184.80 . 0.094.70 . D.374.80 . ?
5.137. 0.294
0.86 ^ 0.051.006. 0.0221 .08 . 0.051 .06 *_ 0.08(2o)
1 .021. 0.015
1.059. 0.0581.012. 0.029
72.5 . 3.068.4 . ?
75 .99 . 5.93
I n - I 1 5 ( n , n ' )
A l -27 (n ,a )A l -27(n ,o )
l n - 1 1 5 ( n , n ' )
l n - 1 1 5 ( n , n ' )
I n -115 (n ,n ' )l n - 1 1 5 ( n , n ' )
N i -58 (n ,p )Absolutel n - 1 1 5 ( n , n ' )
Absolute
Al-27(n,a )l n - 1 1 5 ( n , n ' )
a199.4
1.0061.006
199.4*1.006195.0
196
196.4
105
199.4*
1.006200
o(E)from
1977
0<E)fron.
19821982
olOfrom
197619821982
19B21983
o lEKrom
1973197519761977
o(C)f romo(E) f rom
1982
1982
o(E)rrom
. . .
13)
ENOf/B-U
[61HI
( T a 7 9 )
18116)
1*1l«]
[101
ENOf/B-V
[12118)
[131
ENDF/8-U|14|
161[151
ENDr/B-»
416
TABLE I (cont.)
MANNHART
Reaction
Ti-48(n,p)
V-W(n.p)
V-* l (n ,a }
Te- iMn.p)
lype oT data
Experiment
Recommended
Calculated
Recommended
Exper iment
Calculated
Experiment
Experiment
Experiment
Recommended
Calculated
« >(mb)
12.4 . 1.2
13.8 . 0 . 315.0 . 1.0(2o)13.4 . 1.113.6 . ?
14.20. 0.24
13.47^ 1.70
2 0 . 3 * 1 . 1
18.9 . 0.420.2 . 1.3(2o)22.0 . 0.919.4 . ?
19.43. 0.31
24.06. 2.7019.32
0.42 . 0.010.38 . 0.020.434± 0.0>6(2o)
0.4275.0.0078
O.4O93.O.O422
0.93 . 0.100.713^ 0.059
0.7178.0.0570
(4.30 i O.2O)xlO~2
87 . 384.6 . 2.090.0 . 5.1(2o )92.5 . 5.087.6 . 4.489 . 285. 1 . •>
87.29. 1.13
88.24^ 3.07
ReferenceReact ion
Ni-58(n,p)AbsoluteAbsoluteln-115(n,n ' )
]n -US(n ,n " )
Ni-58(n,p)AbsoluteAbsoluteln -115(n ,n ' )In-115(n,n ' )
AbsoluteIn-115(n,n ' )
Absolute
ln -115(n ,n ' )Al-27(n,o)
In-115(n,n ' )
Nl-58(n,p)AbsoluteAbsoluteIn-115(n,n ' )Al-27(n,«)AbsoluteIn-115(n,n ' )
<mb)
105
-
199.4*
200
105
-
199.4
200
199.4
199.4*
1.006
199.4*
105
-
-
199.2
1.006
-
196.4
Year
1973
1975
1977
1977
1982
0(E) f rom
1973
1975
1977
1977
1982
o(E)f rom
o(E) f rom
1975
1977
1977
o(E) f rom
1977
1982
1977
1973
1975
1977
1978
1982
1982
198 3
a(E)from
Ref.
I'M[HI[13113)
[151
ENOf/8-V
1121
1131
[3]
[151
ENDr/B-U
[ H I
| 3 |
(13!
ENDT/8-V
[31
, 3 ,
[ ' . ,
1121
H31[17]
[°l[18|110]
ENOF/B-U
PART 2-4 417
Reaction
Mn-55(n,2n)
Ni -58(n,p)
Ni -60(n,p)
type of data
Experiment
Recommended
Experiment
Calculated
Recommended
Calculated
E xper intent
Calculated
Calculated
(mb)
1.18 * 0.08
1.450* 0.035
1.45 • 0.06
1.44 * 0.07
1.090* 0.068
l . l l . ?
1 .471* 0.025
1.414»_ 0.0(3
0.58 * 0.15
0.40B* 0.009
0.4079*_0.0092
0.4459.0.0558
105 * 5
116 + 3
118.8* 5.5(2o)
113.4* 4.8
118 * 4
95.0 » 4.5
121 * 2
117.2* ?
115.Bj. 7.3
(8 .94 . 0 . 2 8 ) x lO" '
( 8 . 9 6 5 * 0 . 2 9 7 ) x l O " '
( 7 . 6 0 0 * 0 . 8 2 8 ) x l 0 - '
(B.464*_0. 395 )x l0" '
2.39 * 0.13
3.442* 0.261
6.97 ^ 0.34
6.028
Reference
Reaction
Ni-5B(n,p)
Absolute
ln -115(n ,n ' )
A l -27 (n ,o )
ln -115 (n ,n ' )
i n - 1 1 5 ( n , n ' )
!n -115 (n ,n ' )
Ni-5B(n,p)
fe -54 (n ,p )
Absolute
Absolute
I n - 1 1 5 ( n , n ' )
Al-27(n,o )
J n - l l S l n . n ' )
Absolute
I n - 1 1 5 ( n , n ' )
N i -58 (n ,p )
Ni-58(n,p>
l n - 1 1 5 ( n , n ' )
""k(mb)
105
199.21.006196
196.4
199.4*118
87
-
-
199.4*1.006196
-
196.4
116
118
199.4*
Vear
197319751978198219821983
a(E)from
19761962
o(E)froa
19731975197719771982198219821983
o(E)fro.
1982
•(E)froio(E)from
1982
a ( E ) f r o a
1977
c(C) f rom
Ref .
112]
[ 1 -T J
[°l[9]
ENOF/B-V
(SI
ENDF/B-V
H I ]
1121
113|
[31
[6]
| 9 |
[181
1101
ENOF/B-V
.41
ENDF/B-V
|19,20|
[21]
ENDF/B-U
[31
ENOF/B-U
418
T.'BLEI (cont.)
MANNHART
Type o f d a t a Reference
React ion
Co-59(n,p) Experiment
Recommended
Calculated
1.96 r 0.10
1. 66 • 0.04
1.686* 0.037
ln-U5(n,n') 199.4
Ni-58(n,p) 118
1977
1982
[3]
HI
[22-241
Co-59(n ,a) Experiment
Recommended
Calculated
0.20 . 0.01
0.20 ± 0.01
O.ZIB*_ 0.014
0.222. 0.004
0.2221.0.0039
0.2162.0.0091
N l - 5 8 ( n , p ) 105 1973 |11)I n - 1 1 5 ( n , n ' ) 199.4* 1977 |31A l - 2 7 ( n , a ) 1.006 1982 |6)N i - 5 8 ( n , p ) 118 1962 [4|
o(E)from ENDF/B-V
Co-59(n,2n) Experiment 0.57 0.03
0.406. 0.010
0.4058.0.0101
0.4103.0.0430
ln-115(n,n') 199.4
Ni-58(n,p) 118
1976
1982 1*1
oCElfrom EN0F/6-U
Cu-63(n,Y) Experiment 10.95^10.39^
10.55.
9.649
0 .709 .0 . 6 7 1 .
0.510.30
0.32
0.0170.018
Au-197(n,T)I n -115 (n ,n ' )
AbsoluteN i -58(n ,p )
79.9195
116
19751982
(j(E)rrom
19811982
L2S)141
ENor/e-u
|26|
[41
Cu-6J(n,a) Experiment
Recommended
Calculated
0.6697+0.0130
0.7577.0.0)96
0.6761.0.0379
o (E)fron ENOF/6-U
o(E)fro« (27.28)
Cu-63(n,2n) Experiment
Recommended
Calculated
0.30 0.03
0.183. 0.007
0.1866.0.0071
0.1981.0.0033
In-115(n,n') 199.4
In-HSln.n1) 195
1976 [81
1982 [4|
[71
PART 2-4 419
T y p e o f d a t e
Zn-64(n,p) Experiment 39.4 i 1.0
46.4 i 2.J
41.8 • 1.7
36.2 i 1.5
41.3 . ?
Absolute[n-UXn.n1 )
Al-27(n,a)
In-I15(n,n' )
in-UXn.n1 )
-199.4*
1 .006
196
200
1975
1976
1982
1982
1982
112)
[81
I'l191
[isl
Recommended
Calculated
40.47*_ 0.75
59.23* 2.91 171
Zr-90(n,2n) Experiment 0.267^ 0.015
0.221. 0.006
In-115(n,n' )
Ni-58(n,p)
199.4
lie
1977
1982
13]
Recommended 0.2211.0.0061
Calculated 0.2069*0.00420.2102*0.0041
a(E)froma(E)from [ 1 9 , 2 O |
Nb-93(n,n') Experiment 149 . 10
Calculated 163.6+ 29.1
In-115(n,n ' ) 1982
o(E>rro
129]
[SI
Mo-98(n,-,) Experiment 24.8 *. 1.2
23.2 • 1.4
26.3 . 1.3°
Au-I97(n,Y)
ln-115(n,n')
In-I15(n,n' )
79.9"
199.4*
199.4
1975
1976
1977
|2S|
130|
131
647 ^ 7D
757 » 53
712.2* 21.9
Ni-S8(n,p> 105
199.4*
19731976
oftlfrom
1111
[301
[51
ln-113(nfnI) Experiment I 78.0*^ 7.6
160 • 4
170 • 8
168 • 9
161.9. ?
In-115tn,n 'AbsoluteAl-27(n,n ) 1.006
196196.4
1977
1979
1982
1982
1983
131
1101
Recommended 162.7* 2.5
In-llS(n,T) Experiment 12 5.J* 4.3
139.2*^ 6.0
124. U 3.6
115.6. 5.0
123.2* ?
Absoluteln-115(n
Absolute
In-115(n
In-115(n
,n' )
,n' )
tn' )
-
199
-
196
196
.4*
.4
19711977
1979
1982
1985
|32|
131[31|
[91Hot
Calculated
1 2 6 . U 2 . 8
1 2 1 . 2
420
TABLE I (cont.)
MANNHART
Type of data Reference
React ion
In-115(n,n") Experiment
Recommended
Calculated
186 . 11
198 ^ 5
199.4^ 10.5*
195 ^ 5
201 . 8
196 . 8
196 » 4
18].9+21.6
Absolute
Ni-58(n,p)
Absolute
Absolute?
Absolute
Al-27(n,a )
Absolute
Absolute
1971
1973
1975
1976
1979
19B2
1982
1962
[32]
[11]
I'2J[81
(311
16)
[91
[181
Ta-!81(n,Y) Experiment 105. b +_ 6.1
119.9 • 6.5
89.25+ ?
Au-197(n
[n-115(n
In-115(n
Absolute
Au-197(n
ln-115(n
Absolute
In-115(n
In-115(n
i Y
>n
, n
t Y
, "
. n
,n
)1 )
M
)
• )
' )
• )
7 9 .
199
200
°ch=199
-
196
196
9
. 4 *
98.8b
. 4 *
.4
1975
1977
1982
1971
1975
1977
1979
1982
1983
[2S|
13|(.51
I32J(25]
13]
131]
| 9 |
1101
Au-197(n,-r) Experiment
Recommended
95.5 » 2.3
79.9 » 2.9
119.1 *_ 5.2
76.2 i 1.8
78 . 3
76.0 . ?
77.11. 1.19
76.32o(E)from ENDF/B-U
Au-197(n,2n} Experiment
Recommended
Calculated
4.93 i 0.14
5.80 ^ 0.29
5.50 • 0.14
5.27 i 0.23
5.55 . ?
5 . 5 J 1 . 0.099
5.646
AbsoluteIn-115(n,n')
AbsoluteAl-27(n,a)In-115(n n')
-
199.4-
1.006
196.4
1971
1976
1979
1982
1983
1321
(81
1311
i ( E ) r r o » ENDf/8-V
Th-232(n,f) Experiment
Calculated
89 i 989.4 . 2.7
In -115(n ,n ' ) 199.4 1976 [30]Absolute - 1983 (33|
o(E)from ENDF/B-U
Ih-232(n,Y) Experiment
Calculated
I h -232(n , T ) 1975 [25]
o(E)from ENDF/B-V
PART 2-4 421
Type of data Reference
React ion
Cxpenm
Reeommc
Calculo
ent
nded
ted
1266
1140
1215
1216
1210
1236
± "•111(20)
. 22
t "
• 14
Absolute
Absolute
Absolute
Absolute
1977
1977
1976
19B3
|34|
1131
[351
1361
o U K r o a EN0f/8-V
Np-2)7(n,r) Experiment 1260 . 60
1580 ^100
1570 ^120
1442 ^ 23
1180 .156(20 )
1566 ^ 27
Absolute
Ni -58(n ,p)
In -115 (n ,n '
Absolute
Absolute
U-23B(n,f)
105
199.4
1971
1975
1976
1977
1977
1983
[32|
[••I
[30|
[34]
[13|
|33|
Recommended
Calculated
1556 i 22
1)52 o (E)from ENDf/B-V
U-258(n,r) txpenment M 0 • 25
J08 . 1 7
547 • 6
264 . 27 (2o )
511 • 14
5 2 6 . 0 ^ 6 .5
Absolute
Ni -58(n ,p)
Absolute
Absolute
In -115 (n ,n '
U -2 )5 (n , f )
199.2
1216
1971
1975
1977
1977
1978
1985
[32)
[11]
|34 |
[171
[33|
Recommended
C a l c u l a t e d
5 2 3 . 4 . 5 .6
315 .6 o ( E ) f r o » ENDF/B-V
Pu-239(n,f) Experiment 1800 . 60
1790 i 41
1824 . 35
Absolute - 1971 [32]
Absolute - 1978 (35)
U-255(n, f ) 1216 1983 [33]
Reconraended
Calculated
1811 ^ 25
1792 a(E) f rom ENOF/B-V
Ranormalixad value.b Ooubl* ratio (t— t«xt).C Mo-98(n, TJ + MO 1OO(n, 2n).
422 MANNHART
2.1.3. Experiment by Green [25]
This experiment, involving the measurement of various non-threshold (n, y)reactions, is well documented and could be more justifiably listed in Sec. 2.2.The reason why this has not been done is a peculiarity of the experimental proce-dure. The 2S2Cf spectrum averaged cross-sections of 197Au(n, 7) and 232Th(n. 7)were determined relative to the thermal neutron cross-sections of both reactions.This procedure established correlations between thermal and 252Cf cross-sectionswhich are, however, beyond the scope of the present work and are thereforeomitted owing to basic problems with those data. The experimental method elimi-nated the calibration of the activity-measuring detector system. The fissionneutron flux density of 2S2Cf was based on a source-strength determination via amanganese bath and a distance measurement. Identical foils were irradiated inthe thermal standard neutron field at the United States National Bureau ofStandards (NBS). The thermal neutron flux density was determined by meansof boron films and gold foils. Three additional (n, 7) reactions were measuredby a 'double ratio' procedure. In this case, the 2S2Cf-to-thermal ratio of an unknownreaction was measured relative to the same ratio of 197Au(n, 7).
2.1.4. Experiments by Csikai et al. [30, 8, 3, 17]
The most extensive set of 252Cf data has been measured by a group fromKossuth University at Debrecen, Hungary. For each reaction that was measured,the decay parameters that were used (of the reaction products) were listed.However, further information on the experimental procedure and the necessarycorrections is sparse. Foils of 10 mm diameter were irradiated at a distance ofabout 2 cm from an extended 0.5 mg SR-Cf-1000 source. The neutron sourcestrength was based on a value quoted by the manufacturer. The neutron fluxdensity at the position of the sample was determined using In foils that werevaried at a distance of between 2 and 30 cm from the source, i.e. all measure-ments were relative to the n s In(n , n') cross-section, for which a renormalizedvalue of 199.4 mb was used. The source-sample arrangement was mounted ona thin wire fixed to the ceiling of a large room. The minimum distance fromthe walls was 3 m. In the case of the (n, 7) reactions, the samples were placedinside a cadmium box with a wall thickness of 1 mm. Most activities were mea-sured using a Ge(Li) detector system. The fission cross-sections were determinedat earlier stages of the experiment by solid state track detectors and later by afission chamber. Results were reported from time to time. The sequence startedwith the work of Buczko et al. [30] and ended with the work of Dezso andCsikai [17]. Partial results were either superseded or revised by data publishedlater. This has been allowed for in Table I. Identical results quoted more thanonce are listed under the date of the first publication.
PART 2-4 423
2.1.5. Experiment by Benabdallah et al. [9]
This experiment, performed at the Universite Mohamed V in Rabat, Morocco,is, in its experimental procedure, essentially identical with the experiments ofCsikai et al. (see Sec. 2.1.4). A 20 ng encapsulated 252Cf source was used in anopen-air arrangement 6 m above the ground. The outer dimensions of the cylin-drical source were: diameter 7.8 mm and height 10 mm. The irradiations werecarried out at a distance of (4.3 ± 0.15) mm from the cylinder axis. The free-field neutron flux density was monitored with the U5In(n, n') reaction as afunction of the source-sample distance. The neutron flux density at the targetposition was found to be identical with that of a point source with an effectivedistance of (5.2 ±0.12) mm.
The influence of a backscattered thermal neutron component was investi-gated using the U5In(n, y) reaction measured with and without cadmium shielding.No perturbation due to thermal neutrons was found. In the experiment thestatistical uncertainty dominated the uncertainty of the source strength (about1.5%) and that of the detector efficiency calibration (about 1.5%). Here, too,the neutron source strength was based on a manufacturer's declaration. Thedata must be regarded as measurements relative to n s In(n, n') with a cross-section value of 196 mb.
2.1.6. Experiments by Dezso and Csikai with improved experimentalconditions [15, 10]
A limited set of the earlier measurements was repeated under improvedconditions. The main improvement was the replacement of the indoor irradiationfacility by an outdoor arrangement. Using a 40 ng encapsulated 252Cf source(diameter 7.5 mm, length 14 mm), irradiations were performed in the open airwith the source 12 m above ground and 4 m above the roof of a building. Owingto the fact that an accurate neutron source strength determination was not available,measurements were made relative to the 115In(n, n') reaction. The sample materialwas wound tightly on the surface of the cylinder of the source. The reproducibi-lity of results obtained with this irradiation geometry was of the order of 2% [ 15 ].The geometry was further improved with the use of "compensated beam geometry":two sample foils on opposite sides of the cylindrical source that were irradiatedsimultaneously [10]. This improved the reproducibility from 2 to 1.4%. Furtherimprovements are planned in which samples sandwiched between In foils areirradiated (the data in Ref. [10] partially supersede results contained in Ref. [15]).At present, the estimates of neutron flux density perturbations are incomplete.Therefore, in Refs [15] and [10] only statistical uncertainties are quoted andcomplete uncertainty listing is lacking. In Table I the incomplete uncertaintyof the results is indicated by question-marks.
424 MANNHART
TABLE II. UNCERTAINTY DATA FROM EXPERIMENTS CARRIED OUTATPTB
Resetion
Al-27(n,
Ti-46(n,
Ti-47(n,
Ti-48(n,
Fe-54(n,
Fe-56(n,
Ni-58(n,
Zn-64(n,
In-113(n
In-115(n
In-115(n
In-I15(n
Au-197(n
Au-197(n
i )
3)
P)
P)
?)
3)
3)
3)
n')
y )
n' )
n 1 )
r )2n)
<0 >(mb)
1.006
1J.8
18.9
0.42
84.6
1.450
118.
39.4
160.
124.1
193.
195.
76.2
5.50
Kei.bta.uev•(%>
2.14
2.37
2.29
2.54
2.36
2.39
2.35
2.51
2.42
2.89
2.53
2.46
2.37
2.59
(
100
74
77
69
74
74
75
70
73
61
70
71
74
68
xlOO)
100
74
77
67
66
68
63
66
55
63
65
67
61
100
69
70
69
70
66
68
57
65
67
69
64
100
63
62
63
59
61
51
74
60
62
57
100
71
68
64
66
55
63
65
67
62
100
67
63
65
55
62
64
66
61
100
64
66
55
63
65
68
62
100
62
52
59
61
63
58
100
77
66
90
89
82
100
55
75
75
68
100
67 100
69 88 100
63 80 87 100
It should be noted that the data obtained with the improved irradiationfacility are more consistent with other experiments than the earlier data measuredwith the old facility. This is due to problems with backscattering in the earlierversions of the experiment, where discrepancies up to the order of 40% withother experiments were found.
2.2 Experiments with complete uncertainty information
With the exception of one case, none of the following experiments havedirectly quoted the uncertainty covariance matrix. However, the uncertaintyinformation was sufficiently detailed to allow a reconstruction of this matrix.Besides a short description of the experiment, the covariances are listed in thissection.
2.2.1. Experiments performed at the Physikalisch-Technische Bundesanstalt(PTB)[12,31]
Irradiations were carried out at an outdoor irradiation facility at a position12 m above ground. The sample material surrounded the cylindrical source ina 4 it geometry. The neutron source strength was determined using a water-bathmethod. Absorption and scattering were taken into account by calculating aneffective path length of neutrons through the sample material allowing for thegeometry. In Ref. [12], the metallic sample foils were chemically dissolved andtheir activity compared with radioactive standard solutions. In Ref. [31 ] the
PART 2-4 425
TABLE III. CORRELATION MATRIX FOR NBS FISSION CROSS-SECTIONMEASUREMENTS
Reaction (ratio)
U-235(n, f)
U-238(n, f)/U-235
Np-237(n,f)/U-235
Pu-239(n, f)/U-235
<a> (ratio)(mb)
1216
0.2681
1.123
1.502
Rel. std. dev.(%)
1.62
1.27
1.47
0.97
Correlation(x 100)
100
23 100
- 7 29
- 9 15
matrix
100
36 100
irradiated sample cylinder was cut into pieces and measured with a calibratedGe(Li) detector. Owing to the similarity of both experiments, a commoncovariance matrix has been derived (Table II). The uncertainty informationis quoted in the form of relative standard deviations (Iff level) and a correlationmatrix.
22.2. Fission cross-section measurements at the NBS [37, 38, 36, 33]
The experiment comprises the absolute measurement of the 235U(n, f) cross-section [37] and measurements of 237Np(n, f), 238U(n, f) and 239Pu(n, f) rela-tive to 235U(n, f) [38]. Irradiations were carried out at an indoor facility. Twodouble fission chambers were mounted in a light frame on opposite sides of acalifornium source in a compensated beam geometry. The free-field neutronflux density is based on a neutron source strength determination and a distancemeasurement. The 252Cf source was calibrated in a manganese bath against theRa-Be photoneutron standard source NBS-I. Scattering from support structuresand from wall returns was determined by experiments and calculations. The wall-return effects were diminished by placing a cadmium cylinder around the source-detector assembly. The fission-deposit masses were determined by a multiplicityof techniques, including interlaboratory comparisons with mass standards. Inthe case of the ratio measurements, the fission deposits were arranged in a back-to-back geometry inside the double fission chambers. Orientation effects werecompensated for by turning the fission chambers 180°. The various uncertaintycomponents of the experiment were carefully analysed by Wagschal et al. [39]and a covariance matrix has been derived.
The experimental results have recently been revised [36, 33]. Owing toimprovements in neutron source strength determination, fission-deposit massdetermination and in scattering corrections, all results have been modified.Following the principles given in Ref. [39], the covariance matrix of the revisedvalues has been recalculated (Table HI).
426 MANNHART
TABLE IV. CORRELATION MATRIX FOR THE FISSION CROSS-SECTIONMEASUREMENTS OF ADAMOV et al.
Reaction
U-235 (n, f)
Np-237(n, f)
U-238 (n, f)
Reaction ratios
Np-237/U-235
U-238/U-235
<CT>
(mb)
1266
1442
347
<CT> ratio
1.139
0.2741
Rel. std. dev.(%)
1.44
1.59
1.68
Rel. std. dev.
(%)
1.66
1.80
Correlation matrix(x 100)
100
40 100
34 31 100
Correlation matrix(x 100)
100
39 100
2.2.3. Measurements by Adamov et al. [34]
The fission cross-sections of 235U, 238U and 237Np were determined by thecoincidence technique. A thin Cf layer and a fission deposit of the material beinginvestigated were placed back-to-back inside a double-ionization chamber. Coinci-dences between the spontaneous fission fragments of 2S2Cf and the fragmentsfrom the 2S2Cf neutron-induced fission in the sample material were counted. Theresults obtained are between 5 and 9% higher than those from other experiments.This indicates the possibility of a hidden bias factor in the experiment (for adetailed discussion, see Ref. [40]). To eliminate this bias, the original results werereduced to ratios, the covariances of the original data and of the deduced ratiosbeing listed in Table IV.
2.2.4. Measurements by Spiegel et al. [13]
The irradiation facility was the same as in the NBS experiment described inSec. 2.2.2. Identical foil packets were irradiated in a compensated beam geometry.The packets were arranged around the source with a 60° angular separation, i.e.three identical pairs of packets were irradiated simultaneously. For this specialgeometry, the Cf source was rotated during irradiation to eliminate anisotropiesin the direction of emission. Additionally, perturbations of the free-field neutronflux density due to scattering processes were monitored by Ni detectors enclosedin the packets. The radioactivities induced were measured with sodium iodide andgermanium detectors. The (n, f) cross-sections were based on the detection ofthe radioactive decay of the fission product 140Ba. Uncertainties were quoted
PART 2-4 427
TABLE V. CORRELATION MATRIX FOR THE CROSS-SECTIONMEASUREMENTS OF SPIEGEL et al.
Reaction
Al-27(n,
Al-27(n,
Ti-46(n,
Ti-47(n,
Ti-48(n,
Fe-54(n,
Ni-58(n,
a)
a)
P)
P)
P)
P)
P)
<a>(mb)
1.060
1.060
15.0
20.2
0.434
90.0
118.8
Rel. std. dev.(%)
3.68
3.57
3.27
3.08
4.14
2.88
2.28
Correlation(x 100)
100
95
49
52
39
46
71
100
42
45
33
48
64
matrix
100
79
59
52
79
100
63
55
84
100
41 100
63 79 100
TABLE VI. (n, f) CROSS-SECTION MEASUREMENTS BY SPIEGEL et al.
Reaction
U-235 (n, f)
Np-237(n, f)
U-238 (n, f)
Reaction ratio
Np-237/U-235
U-238/U-235
<o>(mb)
1140
1180
284
<a> ratio
1.035
0.249 i
Rel. std. dev.(%)
4.82
5.73
4.78
Rel. std. dev.(%)
4.24
2.61
Correlation matrix(x 100)
100
69 100
85 70 100
Correlation matrix(x 100)
100
33 100
at the 2a level, though for the calculation of the covariances they have beenreduced to standard deviations (Table V).
In the case of the (n, f) data, a comparison with other experiments has ledto the conclusion that there was an undetected bias factor. As in the case ofthe data contained in Ref. [34], these data have also been reduced to ratios, asshown in Table VI.
428 MANNHART
TABLE VII. CROSS-SECTION MEASUREMENTS BY DAVIS AND KNOLL
Reaction <o> Rel. std. dev. Correlation matrix(mb) (%) (x 100)
U-235(n,f) 1215 1.79 100
Pu-239(n, f) 1790 2.26 59 100
2.2.5. Measurements by Davis and Knoll [35]
The cross-sections of 235U(n, f) and 239Pu(n, f) were determined in thisexperiment (see Table VII). Irradiations were carried out in a compensated beamgeometry, reducing the free-field neutron flux density to a source strength deter-mination and a distance measurement. The neutron source strength was calibratedwith a manganese bath relative to the secondary standard NBS-II (a Ra-Be photo-neutron source). The anisotropy of the 252Cf source was measured with a longcounter and corrected for. Fission events were recorded using solid state trackdetectors.
2.2.6. Measurements by Winkier et al. [26]
This precise experiment for the 63Cu(n, a) cross-section was performedat the NBS irradiation facility. The technique and the correction methods areidentical with the NBS experiments described earlier. After an inspection forimpurities with a Ge(Li) detector, the 60Co radioactivity was measured usingtwo different configurations of large sodium iodide detectors.
2.2. 7. Measurements by Kobayashi et al. [41, 6]
These results were first published in 1979. Various foil packets, at a distanceof 6 cm from a 0.5 mg encapsulated Cf source (5 mm in diameter, 17 mm in height),were irradiated. The neutron flux density was monitored with the 27Al(n, a) andl l sIn(n, n') reactions. Wall-return effects of the indoor irradiation facility weredetermined by neutron transport calculations. The experiment was later comple-tely reanalysed (see Ref. [6]) in order to derive the data and covariances shownin Table VIII.
2.2.8. Measurements by Mannhart [21, 4]
In contrast to earlier PTB measurements, the irradiation geometry wasmodified for this experiment. Disk-shaped samples (10 mm in diameter) of
PART 2-4 429
TABLE VIII. COVARIANCE DATA DERIVED FROM THE EXPERIMENTSOF KOBAYASHI et al.
Hq-2i
ai-27
Al-2
Al-Z7<n.p)/Al-27(n,
5-J2Cn,p)/Al-27(n,a
S-3:?n,p)/Al-27:n,a
V-51<n,p)/Al-27(n,s
Xi-&8(n,p>/Al-27{n,a)
Co-59{n,3 )/Al-27(n,at
Zf>-6a(n,p)/Al-27(n,o)
Jn-113(n,n')/AI-27(n,a
72.
70.
0.71
0.007166
118. i
0.2157
41.t5
ln-HS:n,n>)/Al-2 7(n.«: l'B.9
Au-197{n,2n)/Al-27Cn,«) 5.219
. . 23.7
a .6
5.53.7
5.0
8 . 1
4 .1
J . O
2.7
6 .1
3.6
5 . 5
4 .9
4 . 3
3.B
IOC-
2
2
-1
-
, - 1
2
- 3
-1
100
23 100
19 15 100
8 19 5
6 5 i 5
15 6 5
-4 - 3 -2
-4 -3 -3
16 30 11
18 5 5
28 8 6
10 8 44
0 0 0
13 11 56
32 11 10
100
ui 100
2 2 100
3 Z -5 100
2 -5 31 100
-1:o -10 -13e
-l
10 -25 -26
21 .9 -9
100
9 100
13 17 100
1« 6 6 103
-1 0 0 1C 100
IS 3 8 62 -15 100
20 21 28 15 -1 21 103
TABLE IX. COVARIANCE MATRIX DERIVED FROM MEASUREMENTSOBTAINED BY MANNHART
React ion r a t io C o r r e l a t i o n
(xlOO)
F-19(n,Mg-24(n
A l -27 (n
Mn-55(nCo-S9{n
Co-59(p
Co-59(n
Ni-5S(n
Cu-63(n
Cu-63(nCu-63(n
Zr-90(n
2 n ) / N i - 5 8 ( n ,, p ) / A l - 2 7 ( n ,
, p ) / I n - 1 1 5 ( n
,2n ) /N i -58 (n,p]/Ni-58(n,
, a ) / N i - S 8 ( n ,, 2 n ) / N i - 5 8 ( n
, 2 n ) / N i - 5 8 ( n
, T ) / I n - 1 1 5 ( n, a ) / N i - 5 8 ( n ,
, 2 n ) / I n - 1 1 5 (
, 2 n ) / N i - 5 8 ( n
P)
<•)
, n '
• P)p )
P)
.P>
• P), n ' :
p )
n.n 1
, P )
1.381E-41.998E*0
) 2.459E-2
3.458E-31 .424E-2
1 .877E-3
3 . 4 4 1 E - 3
7 . 5 7 2 E - 5
1 5 . 3 2 8 E - 2
5 . 6 8 6 E - 3
) 9 . J 9 0 E - 4
1 .873E-3
3 . 1 3
2 . 4 0
2 . 4 5
1.93
1.911.432.19
; . i 5
3.002.39
3.33
2.52
100
- 1
- 1 4
30
5
18
27
19
3
7
14
24
100
0
- 1
0
- 1
- 1
0
0
0
- 1
0
100
2
6
19
0
- 6
46
4
42
0
ioa
1 0
37
47
28
5
12
21
36
1 0 0
26
7
16
- 6
27
0
12
100
2 9
17
7
32
15
21
100
24
5
10
19
31
100
- 2
17
8
28
100
- 4
33
3
100
2 100
12 16 100
high-purity metallic foils were irradiated in a sandwich geometry, i.e. each samplewas placed between two neutron flux density monitor foils, with the sandwichpackets almost touching the surface of the cylindrical encapsulation of the source.27Al(n, a), s8Ni(n, p) and n s In(n , n') were used as the monitor reactions. Thesandwich technique allows an accurate determination of the neutron flux densityat the sample position and also reduces the influence of scattering effects whichdisturb the neutron spectrum. Most of the earlier results [ 19] are superseded bythe later data in Ref. [4]. The covariance matrix (Table IX) is given here for thefirst time.
430 MANNHART
TABLE X. COVARIANCE DATA BASED ON MEASUREMENTS BY LAMAZEet al.
Reaction(mb)
Rel. std. dev. Correlation matrix(x 100)
Fe-54(n, p)Ni-58(n, p)
In-115(n, n')
89
121
196
1.731.72
1.85
100
86
46
100
46 100
TABLE XI. LIST OF DATA NOT CONSIDERED IN THIS PART
Reaction
N-14(n, 2n)
F-19(n, p)
Si-28(n, p)
Ti-46(n, 2n)
V-51(n,7)
Mn-55(n,7)
Cu-63(n,7) + Cu-65(n, 2n)
Cu-65(n, 7)
Zn-68(n, 7)
As-75(n, 7)
Sr-84(n, 7)
Sr-86(n,7) + Sr-87(n, n')
Zr-90(n, p)
Mo-92(n, p)
Mo-92(n, a)
Nb-93(n,a)
Nb-93(n, 2n)
Ref.
[3]
[3]
[15]
[3]
[3]
[3][30]
[3]
19]
[30]
[15]
[30]/[9]
[3]
[3]
[3]
[15]
[3]
Reaction
Zr-94(n, 7)
Mo-95(n, p)
Zr-96(n, 7)
Mo-100(n, 7)
Cd-110(n, 7) + Cd-ll l(n,
ln-113(n,2n)
Cd-116(n,7)
Ba-134(n, 7) + Ba-135(n,
Ba-136(n,7) + Ba-137(n,
Ba-138(n, 7)
Hg-198(n, 7) + Hg-199(n,
Pb-204(n, n')
Pa-231(n, f)
U-233(n, f)
Pu-240(n, f)
Pu-241(n, f)
n')
n')
n)
V)
Ref.
[3]
[3]
[3]
[3]
[3O]/[9]
[3]
[30]
[30]/[9]
[30]
[30]/[9]
[30]
[30]
[3]
[33]
[33]
[33]
2.2.9. Measurements by Lamaze et al. [18]
This experiment continues earlier NBS experiments restricted to fissioncross-section alone. The compensated beam geometry was used in its originalversion [37]. Table X lists the covariances derived from a detailed uncertaintylisting.
PART 2-4 431
TABLE XII. NBS EVALUATION OF THE NEUTRONSPECTRUM OF 252Cf [42]
Xcf(E) = [0.6672 v/Eexp(-E/1.42)]/x (E) (E in MeV)
Energy interval(MeV)
0 - 0.25 0.763 + 1.20 E
0.25- 0.8 1.098 - 0.14 E
0.8 - 1.5 0.9668 + 0.024 E
i.5 - 6.0 1.0037-0.000 62 E
6.0 -20 exp[-0.03(E-6.0)]
2.3. Other data
The reactions shown in Table I were selected with regard to their importancein reactor dosimetry. For completeness the remaining reactions, for which 252Cfspectrum averaged data were measured, are listed in Table XI, together with theircorresponding references.
3. CALCULATION OF SPECTRUM AVERAGED CROSS-SECTIONS
For comparison, Table I also gives the results of calculated 252Cf spectrumaveraged neutron cross-sections. In the calculation, a normalized spectral distri-bution, x(E), based on an evaluation performed at the NBS [42], was used. Thisspectrum representation, shown in Table XII, consists of five segment-adjustedcorrection functions, M(E), applied to a Maxwellian with an average energy of2.13 MeV. The correction function above 6 MeV neutron energy has recentlybeen confirmed by an experiment [43]. Somewhat more questionable are thecorrection functions at lower energies [44], though their influence on the calcu-lated results remains small. By assuming a pure Maxwellian between 0 and 6 MeV,i.e. neglecting the correction functions shown for this energy range, the calculatedresults change by less than 0.1% for all of the threshold reactions. For non-thresholdreactions, the maximum deviation is 1.3% for 63Cu(n, 7). This indicates that thedata given in Table XII is sufficient for present purposes (see also Ref. [45]).
The energy-dependent cross-sections used in the calculation are based mainlyon Evaluated Neutron Data File/B-V (ENDF/B-V) data. The integration range isbetween 10~5 eV and 20 MeV, which are the lower and upper energy limits for
432 MANNHART
1.10%
1.10%
1.10%
0.50%
—
1.49%
1.49%
0.50%
-
1.49%
0.50%
TABLE XIII. PART OF THE RELATIVE UNCERTAINTY WHICH IS FULLYCORRELATED BETWEEN VARIOUS EXPERIMENTS
Reference [36] [18] [26] [13] [35]
[36]
[18]
[26]
[13]
[35] 0.50% 0.50% 0.50% 0.50%
ENDF/B-V. The integration was performed with the original point data, in accor-dance with the given interpolation rules, i.e. no pre-processed group cross-sectionswere used. In some cases, cross-section data sets or evaluations not contained inENDF/B-V were also used. For the 27Al(n, a), 47Ti(n, p), S8Ni(n, 2n) and 63Cu(n, a)reactions in particular, data sets given in Refs [14, 16, 19, 20, 27, 28] show betteragreement between experiment and calculation than the data taken from ENDF/B-V.
The uncertainty quotations given for many of the calculated results in Table Iare based on the uncertainties of the a(E) data, the uncertainty from the spectrumrepresentation being discounted. The uncertainties given were propagated fromthe energy-dependent cross-section covariance matrices to the integral valuecalculated.
4. EVALUATION OF A 'BEST' SET OF EXPERIMENTAL DATA
The data in Sec. 2.2 were used for the evaluation of a recommended set of2S2Cf spectrum averaged cross-sections. A generalized least squares technique wasapplied which took into account absolute cross-sections as well as ratios (for details,see Ref. [40]). The different steps in the evaluation up to now have been thefollowing:
Version No. 1 [40]: 17 neutron reactions based on 31 data points.Version No. 2 [4]: 23 neutron reactions based on 48 data points.Version No. 3 (present): 31 neutron reactions based on 63 data points.
Each later evaluation completely supersedes the earlier ones.In Sec. 2.2, only correlations between data belonging to the same experiment
are given. In a few cases correlations also exist between various experiments.These correlations are due to the neutron source strength determination relativeto the standard sources NBS-I or NBS-II and to scattering corrections commonto the various experiments performed at the NBS irradiation facility. The rela-
PART 2-4 433
TABLE XIV. RESULTS OF THE LEAST SQUARESEVALUATION
Reaction
F-19(n,2n)
Mg-24(n,p)
Al-27(n,p)
Al-27(n,o)
S-32(n,p)
Ti-46(n,p)
Ti-47(n,p)
Ti-48(n,p)
W-51(n,p)
Hn-55(n,2n)
Fe-54(n,p)
Fe-56(n,p)
Ni-58(n,p)
Ni-58(n,2n)
Co-59(n,p)
Co-59(n,a)
Co-59(n,2n)
Cu-63(n,Y)
Cu-63(n,o)
Cu-63(n,2n)
Zn-64(n,p)
Zr-90(n,2n )
In-113(n,n' )
In-115(n,Y)
In-115(n,n' )
Au-197(n,y)
Au-197(n,2n)
U-235(n,f)
Np-237(n,f)
U-238(n,f)
Pu-239(n,f)
<a>
(mb)
1.628E-2
2.005E+0
4.892E+0
1.021E+0
7.274E+1
1.420E+1
1.943E+1
4.275E-1
7.178E-1
4.079E-1
8.729E+1
1.471E+0
1.176E+2
8.965E-3
1.686E+0
2.221E-1
4.058E-1
1.055E+1
6.897E-1
1.866E-1
4.047E+1
2.211E-1
1.627E+2
1.261E+2
1.981E+2
7.711E+1
5.531E+0
1.210E+3
1.356E+3
3.234E+2
1.811E+3
Rel. std. dev.
(%)
3.33
2.39
2.16
1.42
3.50
1.68
1.58
1.81
7.95
2.26
1.29
1.73
1.25
3.32
2.21
1.78
2.49
3.08
1.88
3.82
1.85
2.78
1.52
2.19
1.31
1.54
1.79
1.19
1.65
1.72
1.37
tive uncertainties, which are common to more than one experiment, are listedin Table XIII.
It can be seen from this table that out of the total relative uncertainty of1.62% for experiments by Grundl et al. [36], about two-thirds, namely 1.10%,is common to the experiments of Lamaze et al. [18], Winkler et al. [26] and
TABLE XV. CORRELATION MATRIX OF THE EVALUATION
F-19(n,2n)
Hg-24(n,p)
Al-27(n,p)
Al-27(n,a)
5-32(n,p)
ti-46(n,p)
Ti-47(n,p)
H-48(n,p)
V-51(n,p)
Mn-55(n,2n)
re-54(n,p)
re-56(n,p)
Ni-58(n,p)
Ni-58(n,2n)
Co-59(n,p)
Co-59(n,a)
Co-59(n,2n)
Cu-£3(n,T)
Cu-63(n ,a )
Cu-63(n,2n)
Zn-64(n,p)
Zr-90(n,2n)
ln-lDin.n1 )
In-115(n,Y)
In-115(n,n' )
Au-197(n,Y)
Au-197(n,2n)
U-235(n,f)
Np-237(n,r)
U-238(n,f)
Pu-239(n,f )
100
15
8
26
11
23
25
21
4
43
31
21
36
28
23
36
39
17
24
24
19
35
23
16
26
23
20
13
9
8
11
100
27
54
23
33
35
30
6
23
39
35
43
15
23
28
20
18
25
14
32
19
37
25
40
35
31
17
12
10
14
100
44
21
33
36
33
11
25
40
34
44
13
27
39
22
49
29
43
33
19
45
31
54
44
39
19
14
12
16
IK
100
33
57
61
50
12
40
65
57
73
26
40
49
36
29
42
23
55
32
60
41
64
59
52
27
20
17
23
100
22
24
20
3
17
28
24
30
11
17
21
15
13
18
11
22
13
24
16
26
23
19
12
8
7
10
100
60
64
9
34
55
46
63
22
34
42
31
23
35
18
44
27
48
33
52
48
41
23
16
14
19
100
53
10
37
59
50
68
24
37
45
33
24
38
19
47
30
51
35
55
50
45
24
17
15
21
100
9
30
50
42
56
20
30
37
28
23
32
18
39
25
47
33
55
45
39
22
16
13
18
100
7
11
9
12
4
7
9
6
7
8
5
10
5
12
8
13
13
13
5
4
3
4
100
46
32
53
40
34
58
60
21
36
30
29
50
33
23
38
33
30
19
14
12
16
100
56
85
30
46
56
42
28
50
22
50
37
57
39
63
56
50
35
25
22
30
100
59
21
32
39
29
23
34
18
43
26
48
34
53
47
42
23
17
14
20
100
35
54
66
49
30
57
24
54
43
62
43
69
61
54
35
25
22
30
100
30
34
36
11
29
17
19
38
23
16
26
22
20
13
9
8
11
100
49
30
11
43
12
30
31
34
23
38
34
30
20
14
12
17
100
50
23
50
25
37
41
41
29
46
41
37
24
17
15
20
100
19
32
28
27
45
30
21
34
30
27
17
13
11
15
100
16
36
22
16
32
22
39
31
27
13
10
8
11
100
15
31
30
38
26
44
38
33
23
17
15
20
100
18
25
25
17
31
25
22
11
8
7
9
100
24
45
31
48
45
41
21
15
13
18
100
27
19
31
27
24
16
11
10
13
100
57
77
75
65
27
19
17
23
100
53
54
45
19
13
12
16
100
75
64
32
23
20
28
100
74
27
19
17
23
100
23
17
14
20
100
67 100
78 67 100
79 66 67 100
2W
PART 2-4 435
Spiegel et al. [13]. These intercorrelations were taken into account. The evalu-ation of the whole set of data in Sec. 2.2 showed some inconsistencies with regardto the above-mentioned intercorrelations, due mainly to the data sets of Adamovet al. [34] and Spiegel et al. [13]. This indicated that the removal of the suspectedbiases in both experiments, by reducing the data to ratios, was incomplete. Sincethe impression gained is that the uncertainties quoted are underestimated, theuncertainties of both experiments have been enlarged by a factor of 1.5. Thisprocedure has eliminated the inconsistencies to a large extent. The evaluationhas resulted in a x2 value of 39.2, with 32 degrees of freedom, and can beregarded as being sufficiently consistent. The result of the evaluation is givenin Tables XIV and XV. The results are also listed in Table I as recommendedvalues.
An inspection of Table XIV shows that out of a total of 31 reactions,18 have relative uncertainties less than 2% and 24 reactions have less than2.5%. Those reactions with uncertainties greater than 2.5% are in all casesresults based on a single experiment. This indicates that there is a need for moreexperiments to validate existing results and to improve the overall accuracy tothe data.
REFERENCES
[1] WAGSCHAL, J.J., MAERKER, R.E., BROADHEAD, B.L., in Reactor Dosimetry (Proc.4th ASTM-EURATOM Syrap. Gaithersburg, MD, 1982), Vol. 1, US Nuclear RegulatoryCommission, Washington, DC, Rep. NUREG/CP-0029 (1982) 79.
[2] MANNHART, W., Nucl. Sci. Eng. 77 (1981) 40.[3] DEZSO, Z., CSIKAI, J., in Neutron Physics (Proc. 4th All-Union Conf. Kiev, 1977),
Vol. 3, Atomizdat, Moscow (1977) 32.[4] MANNHART, W., in Nuclear Data for Science and Technology (Proc. Int. Conf. Antwerp,
1982) (BOCKHOFF, K.H., Ed.), Reidel, Dordrecht (1983) 429.[S] STROHMAIER, B., TAGESEN, S., VONACH, H., Physics Data 13-2, Fachinformations-
zentrum, Karlsruhe (1980).[6] KOBAYASHI, K., KIMURA, I., MANNHART, W., J. Nucl. Sci. Technol. 19 (1982) 341.[7] TAGESEN, S., VONACH, H., STROHMAIER, B., Physics Data 13-1, Fachinformations-
zentrum, Karlsruhe (1979).[8] CSIKAI, J., DEZSO, Z., Ann. Nucl. Energy 3 (1976) 527.[9] BENABDALLAH, H., PAIC, G., CSIKAI, J., in Nuclear Data for Science and Technology
(Proc. Int. Conf. Antwerp, 1982) (BOCKHOFF, K.H., Ed.), Reidel, Dordrecht (1983) 421.[10] DEZSO, Z., CSIKAI, J., Measurements of Cf-252 Spectrum Averaged Cross-Sections,
The Cf-252 Fission Neutron Spectrum (Proc. IAEA Consultants Meeting Smolenice,Czechoslovakia, 1983) (LEMMEL, H.D., CULLEN, D.E., Eds), IAEA/InternationalNuclear Data Committee, Vienna, Rep. INDC(NDS)-146 (1983) 225.
[11] KIROUAC, G.J., EILAND, H.M., SLAVIK, C.J., in Irradiation Experimentation inFast Reactors (Proc. Int. Conf. Jackson Hole, Wyoming, 1973), Office of Scientific andTechnical Information, US Department of Energy, Oak Ridge, TN, Rep. CONF-730910(1973)412.
436 MANNHART
[12] ALBERTS, W.G., GUNTHER, E., MATZKE, M., RASSL, G., in Reactor Dosimetry (Proc.1st ASTM-EURATOM Symp. Petten, Netherlands, 1975), Part 1, Commission of theEuropean Communities, Brussels, Rep. EUR-5667 (1977) 131.
[13] SPIEGEL, V., EISENHAUER, CM., GRUNDL, J.A., MARTIN, G.C., in Reactor Dosimetry(Proc. 2nd ASTM-EURATOM Symp. Palo Alto, CA, 1977), Vol. 2, US Nuclear RegulatoryCommission, Washington, DC (1978) 959.
[14] TAGESEN, S., VONACH, H., Physics Data 13-3, Fachinformationszentrum, Karlsruhe(1981).
[15] DEZSO, Z., CSIKAI, J., in Nuclear Data for Science and Technology (Proc. Int. Conf.Antwerp, 1982) (BOCKHOFF, K.H., Ed.), Reidel, Dordrecht (1983) 418.
[16] SMITH, D.L., MEADOWS, J.W., MANNHART, W., unpublished.[17] DEZSO, Z., CSIKAI, J., Average Cross-Sections for the 2S2Cf Neutron Spectrum, Nuclear
Data for Reactor Dosimetry (Proc. Advisory Group Meeting Vienna, 1978), IAEA/International Nuclear Data Committee, Vienna, Rep. INDC(NDS)-103/M (1979) 176.
[18] LAMAZE, G.P., McGARRY, E.D., SCHIMA, F.J., in Nuclear Data for Science andTechnology (Proc. Int. Conf. Antwerp, 1982) (BOCKHOFF, K.H., Ed.), Reidel, Dordrecht(1983)425.
[19] WINKLER, G., PAVLIK, A., VONACH, H., PAULSEN, A., LISKIEN, H., in NuclearData for Science and Technology (Proc. Int. Conf. Antwerp, 1982) (BOCKHOFF, K.H.,Ed.), Reidel, Dordrecht (1983) 400.
[20] PAVLIK, A., WINKLER, G., Evaluation of the s8Ni(n, 2n)S7Ni Cross-Sections,IAEA/International Nuclear Data Committee, Vienna, Rep. INDC(AUS)-9/L (1983).
[21] MANNHART, W., in Reactor Dosimetry (Proc. 4th ASTM-EURATOM Symp. Gaithersburg,MD, 1982), Vol. 2, US Nuclear Regulatory Commission, Washington, DC, Rep. NUREG/CP-0029( 1982) 637.
[22] SMITH, D.L., MEADOWS, J.W., Nucl. Sci. Eng. 60 (1976) 187.[23] SMITH, D.L., MEADOWS, J.W., Argonne National Lab., Argonne, IL, Rep. ANL/NDM-13
(1975).[24] VASILIU, G., MATEESCU, S., The analysis of the 59Co(n, p)S9Fe and S4Fe(n, a)slCr
Cross-Sections for their Use in Reactor Dosimetry, Nuclear Data for Reactor Dosimetry(Proc. Advisory Group Meeting Vienna, 1978), IAEA/International Nuclear DataCommittee, Vienna, Rep. INDC/(NDS)-103/M (1979) 26.
[25] GREEN, L, Nucl. Sci. Eng. 58 (1975) 361.[26] WINKLER, G., SPIEGEL, V., EISENHAUER, CM., SMITH, D.L., Nucl. Sci. Eng. 78
(1981)415.[27] WINKLER, G., SMITH, D.L., MEADOWS, J.W., Nucl. Sci. Eng. 76 (1980) 30.[28] WINKLER, G., private communication, 1982.[29] ALBERTS, W.G., HOLLNAGEL, R., KNAUF, K., MATZKE, M., PEfiARA, W., in
Reactor Dosimetry (Proc. 4th ASTM-EURATOM Symp. Gaithersburg, MD, 1982),Vol. 1, US Nuclear Regulatory Commission, Washington, DC, Rep. NUREG/CP-0029(1982)433.
[30] BUCZKO, M., in Californium-252 Utilization (Proc. Int. Symp. Paris, 1976) (BERGER, R.L.,CORMAN, W.L., Eds), Vol. 2, Office of Scientific and Technical Information, US Departmentof Energy, Oak Ridge, TN, Rep. CONF-760436 (1979) IV-19.
[31] MANNHART, W., ALBERTS, W.G., Nucl. Sci. Eng. 69 (1979) 333.[32] PAUW, H., ATEN, A.H.W., J. Nucl. Energy 25 (1971) 457.[33] GRUNDL, J.A., GILLIAM, D.M., Fission Cross-Section Measurements in Reactor Physics
and Dosimetry Benchmarks, the Cf-252 Fission Neutron Spectrum (Proc. IAEA ConsultantsMeeting Smolenice, Czechoslovakia, 1983) (LEMMEL, H.D., CULLEN, D.E., Eds),IAEA/International Nuclear Data Committee, Vienna, Rep. INDC(NDS)-146 (1983) 241.
PART 2-4 437
[34] ADAMOV, V.M., et al., in Neutron Standards and Applications (Proc. Int. Symp.Gaithersburg, MD, 1977), US National Bureau of Standards Special Publication 493,US Government Printing Office, Washington, DC (1977) 313.
[35] DAVIS, M.C., KNOLL, G.F., Ann. Nucl. Energy 5 (1978) 583.[36] GRUNDL, J., GILLIAM, D., McGARRY, E.D., EISENHAUER, C, SORAN, P.,"Revised
Values for the 2s2Cf Fission Spectrum-Averaged Cross-Section for the 235U Fission", TheCf-252 Fission Neutron Spectrum (Proc. IAEA Consultants Meeting Smolenice,Czechoslovakia, 1983) (LEMMEL, H.D., CULLEN, D.E., Eds), IAEA/InternationalNuclear Data Committee, Vienna, Rep. INDC(NDS)-146 (1983) 237.
[37] HEATON, H.T., II, GRUNDL, J.A., SPIEGEL, V., GILLIAM, D.M., EISENHAUER, C,in Nuclear Cross-Sections and Technology (Proc. Int. Conf. Washington, DC, 1975),US National Bureau of Standards Special Publication 425, US Government PrintingOffice, Washington, DC (1975) 266.
[38] GILLIAM, D.M., EISENHAUER, C, HEATON, H.T., II, GRUNDL, J.A., ibid, p.270.[39] WAGSCHAL, J.J., MAERKER, R.E., GILLIAM, D.M., in Reactor Dosimetry (Proc.
3rd ASTM-EURATOM Symp. Ispra, Italy, 1979) (ROTTGER, H., Ed.), Vol. 2,Commission of the European Communities, Brussels, Rep. EUR-6813 (1980) 683.
[40] MANNHART, W., PEREY, F.G., in Reactor Dosimetry (Proc. 3rd ASTM-EURATOMSymp. Ispra, Italy, 1979) (ROTTGER, H., Ed.), Vol. 2, Commission of the EuropeanCommunities, Brussels, Rep. EUR-6813 (1980) 1016.
[41 ] KOBAYASHI, K., KIMURA, I., in Reactor Dosimetry (Proc. 3rd ASTM-EURATOMSymp. Ispra, Italy, 1979) (ROTTGER, H., Ed.), Vol. 2, Commission of the EuropeanCommunities, Brussels, Rep. EUR-6813 (1980) 1004.
[42] HEATON, H.T., II, GILLIAM, D.M., SPIEGEL, V., EISENHAUER, C, GRUNDL, J.A.,in Fast Neutron Fission Cross-Sections of U-233, U-238, Pu-239 (Proc. NEANDC/NEACRPSpecialists' Meeting, Argonne, IL, 1976) (POENITZ, W.P., SMITH, A.B., Eds), ArgonneNational Labs., IL, Rep. ANL-76-90 (1976) 333.
[43] MARTEN, H., SEELIGER, D., STOBINSKI, B., in Nuclear Data for Science and Techno-logy (Proc. Int. Conf. Antwerp, 1982) (BOCKHOFF, K.H., Ed.), Reidel, Dordrecht (1983)488.
[44] The Cf-252 Fission Neutron Spectrum, (Proc. IAEA Consultants Meeting, Smolenice,Czechoslovakia, 1983) (LEMMEL, H.D., CULLEN, D.E., Eds), IAEA/InternationalNuclear Data Committee, Vienna, Rep. INDC(NDC)-146 (1983) 23.
[45] MANNHART, W., Part 1-4, this Handbook.
Part 3
CHARGED PARTICLE ACTIVATION
3-1. CALCULATION OF EXCITATIONFUNCTIONS FOR CHARGED PARTICLEINDUCED REACTIONS
R. NOWOTNY, M. UHLInstitut fur Radiumforschung
und Kernphysik,Universitat Wien,Vienna, Austria
Abstract
CALCULATION OF EXCITATION FUNCTIONS FOR CHARGED PARTICLE INDUCEDREACTIONS.
Excitation function data are required for various purposes. A means for estimatingnuclear excitation functions if experimental data are missing is the calculation of cross-sectionswith one of the available computer codes. An introduction to the theory behind the reactionmechanism and the various nuclear parameters used is given to aid the potential user in theapplication of such codes. Various examples are given of excitation functions of reactionsused for the production of radioisotopes that are of mainly medical interest. The resultsindicate that calculated excitation functions, at least for proton induced reactions obtainedwith a standard set of input parameters, could be used as estimates with adequate accuracy.For projectiles other than protons, the results are less satisfactory.
1. INTRODUCTION
Cross-section data for charged particle induced nuclear reactions are requiredin a number of fields. While data on excitation functions are often needed forradioisotope production, they are also of interest, for example, in activationtechniques or in radiobiology. However, the situation with regard to chargedparticle cross-section data is less satisfactory when compared with neutroncross-section data. In the latter case, a large quantity of data has been collectedcovering, at a minimum, an energy range of up to several MeV for almost all stableisotopes. Many comprehensive compilations on neutron data exist and thesedata are also available from data files.
For charged particle induced reactions, data on a larger number of reactiontypes are of interest as the energy of the incident particle is usually higher thanin the applications considered in reactor physics. Also,charged particle inducedreactions have been of less importance in technological applications, with the resultthat the situation for charged particle reaction data is less advanced. Compilations ofintegral cross-section data have been published by the Karlsruhe Charged Particle
441
442 NOWOTNY and UHL
Group [ 1 ] and the National Nuclear Data Center at Brookhaven National Labora-tory (BNL) in Upton, New York [2].
Excitation functions which represent variations of cross-sections for parti-cular reactions with incident energy can be used in radioisotope production to
(1) Determine the particle energies required for a particular reaction type.(2) Calculate the radioisotope production yield which can be expected for a
particular reaction and a given target matrix.(3) Calculate the production yields for radionuclidic impurities, which help to
determine the need for isotope-enriched target materials.
For any radioisotope the optimum conditions for production will depend onmany factors. A large quantity of data, particularly at higher particle energies,would be required to determine production yields and contaminants of allcompeting reactions. Only if these data are available can an a priori assessmentbe made of the advantages and limitations of the various production methods.The situation is even more complex if indirect production regimes are assumedto take advantage of half-life discrimination of contaminants in the decay of theactivation products.
Quite often only radioisotope production yield data are available in theliterature. While such data are important for production purposes, a better under-standing of the relationship between the various factors contributing to productand contaminant yield is obtained from excitation function data. In particular,it is easier to assess the consequences of a variation in irradiation conditions,which for various reasons might be difficult to be made identical at differentcyclotrons. Indeed, excitation functions are just the beginning. Thereremain many more factors that are important in radioisotope production. Theseinclude suitably chosen 'targetry' (target composition and material, target cons-truction and transfer of dissipated heat) and radiochemical procedures (remotetarget handling, chemical processing, radiochemical and radiopharmaceuticalquality assurance).
In the event that excitation functions are required, but the experimentaldata are missing, two possible means are available to obtain estimates. Kelleret al. [3] have devised a semi-empirical method by which characteristic excitationfunction parameters (starting energy, maximum cross-section, the energy positionof the maximum cross-section, the cross-section of the tail and width at half-maximum cross-section) are derived from a standard set of data. Another meansis the application of one of the computer codes available for the calculation ofnuclear cross-sections. These codes were developed mainly to gain theoreticalunderstanding of nuclear reaction processes, but they have also been used forcross-section evaluations, primarily neutron induced reactions.
The accuracy with which excitation functions can be reproduced usingcomputer codes depends on several factors which will be discussed below. Themeasure for the accuracy of calculated excitation functions is the experimental
PART 3-1 443
data. According to Qaim [4], experimental cross-section errors range in generalfrom about 10 to 15%, increasing for low yield data to about 25%. Errors inparticle energy cannot often be found in the literature but, depending on particleand energy errors, could extend to about ± 2 MeV or more. This is of particularimportance when the initial rise of an excitation function from various sourcesis compared.
Certainly the discrepancies found in experimental data from various authorsfor the same reaction often exceed the quoted error figures, but this reflects thedifficulties encountered in the measurement of excitation functions. A globaltest for the quality of calculated cross-section data can be made by a calculationof radioisotope production yields and by a comparison with data from theliterature [3, 5].
In what follows, an introduction to theoretical principles will be given inorder to aid the potential user in the application of the codes and in the under-standing of their input parameters. Some examples of proton induced reactionswill be given and the usefulness of calculations for other projectiles will also bediscussed.
2. MODELS AND PARAMETERS
This section presents a short outline of the reaction models most importantfor the calculation of the cross-section for the production of radioisotopes(activation product cross-sections). All of the following considerations refer to incidentenergies between a few MeV and several tens of MeV. For most reactions employedin the production of radioisotopes, fission competition is not important. Therefore,the treatment of fission will not be described.
2.1. Reaction mechanisms and their importance for activation product cross-sections
In general, one can distinguish between two extreme reaction mechanisms:direct reactions (DIR) which involve only a few degrees of freedom of the manynucleon systems under consideration and compound nucleus reactions (CNR),which are characterized by the participation of many active degrees of freedom.Cross-sections for DIR are calculated by solving explicitly the scattering problemfor a (simplified) dynamic model. The theoretical treatment of CNR, on the otherhand, is based essentially on statistical assumptions. In addition to these twoextreme mechanisms, there are also pre-equilibrium reactions (PER) or precom-pound reactions which, in terms of complexity, are situated between DIR andCNR. For a given reaction all three mechanisms contribute to the extent possible,depending on the type of reaction (projectile and ejectile), the incident energyand the excitation energy of the residual nucleus.
444 NOWOTNY and UHL
At incident energies beyond a few MeV, the activation products result essen-tially from gamma ray de-excitation of a large number of highly excited states.The cross-sections for the formation of those levels by reactions with one orseveral emitted particles can often be calculated quite reliably by a combinationof models for PER and CNR.
Direct reactions occur mainly as binary processes. They preferentiallypopulate 'simple' low lying levels of the residual nucleus [6] (e.g. collective statesin the case of inelastic scattering and states of predominantly single particlecharacter in one nucleon transfer reaction, such as (d, p) or (p, d). In manyapplications the neglect of DIR is justified as the resulting errors are of the sameorder as the inherent uncertainties of the PER and CNR models. However,special care is required in cases of unusually large DIR contributions as, forexample, reactions on very light or on permanently deformed target nuclei andreactions induced by weakly bound projectiles, such as deuterons or 3He particles.
It is difficult to give a general assessment of the errors resulting from theneglect of DIR as the effect critically depends on the case under considerationand on the parameters used for PER. For a careful calculation of an unknowncross-section, it is important to investigate how well the employed models repro-duce reliable experimental data for neighbouring target nuclei.
In spite of these restrictions, the discussion in this paper concentrates onthe application of models for CNR and PER mechanisms as these lend themselveseasier to routine applications. The angular distribution of the reaction productsis irrelevant for activation product cross-sections and thus will not be discussed.
2.2. The compound nucleus evaporation model
This model is based on Bohr's concept of the compound nucleus [7] as anintermediary stage of a nuclear reaction. The compound nucleus (CN) is assumedto be in thermal equilibrium. Hence, apart from restrictions due to conservedobservables, its formation and decay are independent of each other. Further,the decay of the CN is governed only by phase space and barrier penetrabilities.The cross-section formulas resulting from this concept depend on the conservationlaws which are taken into account.
The initial and final states of a binary nuclear reaction A(a, b)B (i.e. thechannels) are characterized by indices a, 0,..., which specify the fragmentationof the many-nucleon system into light and heavy subsystems (a, A), (b, B),...and by the intrinsic states of the fragments. Their excitation energies, spins andparities for a given fragmentation y are denoted, respectively, by (e , E7), (i ly)and (ir II )• For reactions of interest in the present context, one assumes thatthe light fragments and the target are in their ground states: that is, Ea = 0 ande = 0, where a denotes the entrance channel and y an arbitrary exit channel.
Conservation of energy, angular momentum and parity require the followingrelations to hold for entrance channel a and exit channel /3:
PART 3-1 445
= n =
Here E, I and II denote the excitation energy, spin and parity of the CN, respec-tively, while Sa, So,... are the separation energies and ea, €„, ... and 2a , 2^, ...represent the kinetic energy and the orbital angular momentum of the relativemotion of the fragments, respectively.
The simplest expression for the cross-section
which, for a binary reaction, results from the CN concept, accounts only forenergy conservation (Eq. (la)) and was proposed by Weisskopf and Ewing [8]:
(2)
The first factor oa(ea) represents the cross-section for the formation of the CNvia the entrance channel and the second one represents the branching ratio forits decay into the channel with kinetic energy around e^. The density of excitedstates of the residual nucleus around the excitation energy
Sa ~ S/3 ~
is denoted by O)g(Eo). Under the assumption of time reversal invariance, thebranching ratio can be evaluated in terms of the cross-sections a (e ) for theformation of the CN in all open channels (the 'inverse cross-sections') [8]:
, Eg) g g g g )
E S
where k^ represents the wavenumber corresponding to the channel energy eo.The sum and integration in the denominator comprise all open channels. Theauxiliary quantities oAe^) and co (E_), which enter in Eqs (2) and (3), are
446 NOWOTNY and UHL
discussed further in Sec. 2.4. The resulting particle spectra have a shape characte-ristic of an 'evaporation spectrum' as a consequence of the assumption of the CNbeing in thermal equilibrium.
For the calculation of activation product cross-sections, one assumes thatbeyond the particle emission thresholds gamma decay is negligible compared withparticle emission. Therefore, the activation product cross-section c^cJ(ea) is givenby the sum of the populations of the states of the residual nucleus with excita-tion energies up to the minimum particle emission threshold Smin
c°min
(4)
as only those states will ultimately populate the ground state by gamma ray cascades.The population of states with Eo> Sm i n gives rise to multiple particle emission.
The Weisskopf-Ewing (WE) approach can easily be extended to reactions withmultiple particle emission by assuming that the particles are emitted sequentiallyand that each of the intermediary nuclei can be treated as a 'compound nucleus',the decay of which is governed by the branching ratio given in Eq. (3). Thus theactivation product cross-section for a ternary reaction A(a, bc)C is given by
f iyEj.eo) r ry(E2,ey)rt SCI (<~ \ n (£: \ I H P —-
S 0(5)
where E! and So refer to the first and E2 and S to the second CN. Smin andcjy(Ey) represent the minimum particle emission threshold and the state densityof the final reaction product, respectively. Obviously, Eq. (5) can be generalizedto the evaporation of an arbitrary number of particles.
The WE formalism offers a fast and simple method to estimate the contribu-tion of CNR to activation product cross-sections. Calculations based on it willbe referred to as 'WE calculations'.
A refined version of the CN evaporation model also considers the conserva-tion of angular momentum and parity. The results are generalizations of thewell-known Hauser-Feshbach formula [9]. The ansatz (2) for the cross-sectionis replaced by
r(E, I, U;e8,afe«. V U«' I n ) r ( E I II)
in
PART 3-1 447
where the sum is over all angular momenta and parities (I, II) of the CN. Thequantities oa(ea, la, Ua; III) and PQ(EQ, L, Ua) represent, respectively, thecross-sections for the formation of the CN in states of given quantum numbers(I, II) and the density of levels around Efi with quantum numbers (Ig, fig) of thefinal nucleus. While for a higher excitation energy the level density is obtainedfrom statistical considerations, the experimental information on the actual levelscheme is used near the ground state instead of a level density formula. Thegeneralization of Eq. (3) for the branching ratio reads
r(E, i, n ; Eg, i
r(E, i, n)g ,ng; I, II)
2 2 (2i7 + 1)(2I7 + 1 ) * / ^ dEyk2yoy(er ly, Uy, I,
(7)
In the 'channel spin coupling scheme', the quantities ay(ey, I , II ; I, FI) are relatedto the optical-model transmission coefficients Tg (e ) by
7
a(ey,ly,Uy;l,U)
I7+ i7 ' T + S 7
21+1 r-i r->
i_l 1
s 7 =| I 7 - i T l S 7=|I-s 7 l
(8)
The limits of the sums over the channel spin ?7 = L, + IL and over £ accountfor the angular momentum conservation (Eq. (lb)), while the Kronecker deltaguarantees parity conservation (Eq. (lc)). For the alternative j-coupling scheme,see, e.g., the review by Vogt [10]. In terms of a 7 ( e 7 l 7 l l 7 , III) andp(E7 , I7, II7),the corresponding quantities of the Weisskopf-Ewing approach are given by
in 7 8=0T 7
, i7,n7)i n7 7
448 NOWOTNY and UHL
From the general theory of CNR (see, e.g., Refs [11, 12]), it is known thatEq. (6) together with Eqs (7) and (8) hold only for non-elastic processes in thelimiting case of many open channels. In particular, they do not consider thewidth fluctuation correction and compound elastic enhancement. In connectionwith activation product cross-sections at energies beyond a few MeV, both effectsare of little importance.
The calculation of the cross-sections for the production of the residualnuclei requires a suitable generalization of Eq. (4) for binary reactions and Eq. (5)for processes with multiple particle emission. The theory can be improvedsubstantially by explicitly including gamma ray cascades. Photons are treatedin the same way as particles with transmission coefficients, depending on the type(El, Ml, E2, ...) of electromagnetic multipole radiation. Details regarding thecombination of gamma ray cascades and multiple particle emission can be found,e.g., in Ref. [13]. As a consequence of this model extension, the gamma raycompetition with particle decay (an effect which critically depends on the spinsof the levels involved [14, 15]) can be treated properly. Furthermore, theinclusion of gamma ray cascades is required for the calculation of the productionof isomeric levels.
Calculations based on the CN model with angular momentum and parityconservation will be referred to as the Hauser-Feshbach (HF) calculations.Owing to the various angular momentum sums, computer codes which performHF calculations require more time and storage than those designed forWE calculations. On the other hand, the competition between the variousdecay modes of the CN depends on the angular momentum. This effect, whichis especially pronounced near the maximum spin allowed for a given excitationenergy (the 'yrast spin'), cannot be reproduced by a WE calculation. The choicebetween the expensive HF approach and the fast, but less precise, WE approachdepends on the type of cross-section to be calculated and on the required accuracy.For isomeric state production cross-sections, a HF calculation is indispensable.
Some of the deficiencies of WE calculations can be removed by the "s-waveapproximation" proposed by Blann and Merkel [16]. It is assumed that the spindistribution of the residual nuclei is the same as that of the (first) CN: this wouldbe true if all particles were emitted in s states of relative motion. As a consequenceof this assumption, HF calculations may be replaced by WE calculations for eachvalue I of the spin of the CN. An upper limit for the gamma ray competition isobtained by assuming that for a given angular momentum I, all states withexcitation energy
decay by gamma ray cascades; here Smin is the minimum particle separationenergy and Em i n (I) denotes the yrast level, i.e. the minimum excitation energyrequired for angular momentum I.
PART 3-1 449
Isospin, besides angular momentum, also plays an important role in CNR.The main effect of isospin conservation is to enhance inelastic scattering ofprojectiles with a proton excess as, for example, protons or 3He particles.Approaches that included isospin in the consideration of isospin mixing wereproposed by several authors and were compared by Lane [17].
2.3. Models for pre-equilibrium emission
With increasing bombarding energy the properties of the emitted particlessignificantly deviate from the predictions of the CN evaporation model. Insteadof a pure evaporation spectrum and symmetry around 90°, one observes an excessof high energy particles which are emitted, preferentially, in a forward direction.These effects are interpreted as being due to emission before the compositesystem (which initially is formed in simple states and equilibrates through intra-nuclear transitions) has reached the thermal equilibrium characteristic for the CN.
By considering pre-equilibrium (PE) emission, the cross-section da^/deaconsists of two contributions:
representing the decay of the composite system before and after equilibration.The equilibrium contribution ^o^Jbeo can be calculated in the frame of the CNevaporation model described in Sec. 2.2. The factor qpre represents the fractionof the incident flux which survives PE emission. Many cross-section calculationsconsider PE emission only for the first emitted particles and treat multipleparticle emission as CN evaporation. According to Blann and Vonach, thisprocedure seems justified for incident energies up to about 50 MeV [18].
The enhanced high energy portion of the spectra of particles emitted in thePE stage is also of crucial importance for activation product cross-sections.Therefore, pre-equilibrium reactions have to be considered for incident energieslarger than about 8 MeV.
Although several fundamental theories of PER were proposed over the years(see Refs [19-21 ]), only the two most popular phenomenological PE models -the exciton and the hybrid models — which are especially convenient for routinecalculations, are discussed here. These models are conceptually different, thoughwhen suitably parametrized both successfully reproduce experimental data.
2.3.1. The exciton model
In this model, which was suggested by Griffin [22, 23], the states of thecomposite system are characterized only by the excitation energy and the number
450 NOWOTNY and UHL
of excited particles p and excited holes h. Particles and holes are defined withrespect to a closed shell reference state and are collectively called excitons. Theexciton number n is given by n = p + h. Starting from a simple particle-holeconfiguration, n0 = p0 + h0 , which depends on the projectile (see Sec. 2.4.3),the system equilibrates through a series of two-body interactions and emitsparticles from all intermediate stages. Two-body interactions may change theexciton number by amounts of An = 2, 0, —2, corresponding to the creation,scattering and annihilation of a particle-hole pair. The rates for these internaltransitions averaged over all states of an n = p + h exciton configuration aredenoted by A^n, E), A'0(n, E) and A\ (n, E).
The simplest expression which results from this concept for the PE contri-bution (9a^fle/9eg)(ea, e«) of the cross-section reads
n-n0(An=2)
where Ag(eg: n, E) represents, for states with n excitons, the average rate ofdecay into fragmentation j3 with channel energy es, and Ac (n, E) the total decayrate into the continuum, i.e. the sum of A»(e»; n, E) over all open channels. Thesum over the exciton number n extends up to the most probable value n atequilibrium which, in terms of the single particle state density g, is approximatelygiven by rf = •s/2gE. The quantity Dn(E) represents the fraction of the initialpopulation of the composite system which has survived emission in the previousconfigurations n0, n0 + 2,... , n —2. For n > n0, this 'depletion factor' is givenby
A > , E)
v = no(Ai> = 2) ' +
while, per definition, Dn (E) = 1. The factor qpre in Eq. (9) is given byqPre = D-+2(E). °
Equations (10) and (11) essentially rely on the assumption A^n, E) > Ax_(n, E),which holds for small exciton numbers n, as can be seen from phase space argu-ments; the main contributions to the PE spectrum stem from small values of n.In general the equilibration process is described by a version of the Pauli masterequation which can be represented as a system of first-order differential equationsin time [24] or as stochastic equations of a random walk problem [25, 26]. Themaster equation approach also allows a 'unified' treatment of PE emission andequilibrium decay [26]. Nevertheless, considering the phenomenological nature
PART 3-1 451
of the model itself, Eqs (10) and (11) represent reasonable approximations tothe solution of the master equations.
The cross-sections defined in Eqs (10) and (11) first require rates for internaltransitions. A widely used method to calculate these quantities relies on Fermi'sgolden rule:
A^ n (n ,E)=-^ |M| 2 w A n (n ,E) (12)
where |M|2 is the averaged squared matrix element of residual interactions (seeSec. 2.4.3) and ^ A n (n , E) is the number of accessible final states. As an exampleof the many evaluations of w^n(n, E), we quote the often-used results ofWilliams [27]
w+(n,E) = (l/2)g3E2/(n + 1)
with the correction factor (1/2) of Oblofcinsky et al. [28]. In a different approach,Gadioli et al. determined the dependence of A\n, E) on n and E on the basis ofthe nucleon-nucleon cross-section in nuclear matter and adjusted the absolutemagnitude by comparison with experimental data [29]. The results are independentof the mass number and are tabulated in Ref. [30].
Particle emission rates are in general obtained by applying the principle ofdetailed balance. For fragmentation |3, i.e. the emission of particle b with trb
protons and i>b neutrons, one obtains
Hgea Cj(p-p«, ha, Ea)
A<^: P h E ) - ( 2 i + l )R(p) j i gq(q) ^ J (13)
where Mb denotes the reduced mass and p» = ;rb + i>b is the number of nucleonsof the light fragment. The quantities oj(p, h, E) and oj(p-po,h, Eg) representstate densities with a specified number of particles and holes and refer to thecomposite system and the residual nucleus, respectively. The factor Rg(Pg)stands for the probability that po-emitted nucleons have the right combinationof protons and neutrons and thus account in an approximate way for proton-neutron distinguishability. Simple expressions for the quantity Rg(pg), whichdepends on the projectile, were derived by Cline [31 ] and Kalbach [32] and byBirratari et al. [33]. A more accurate treatment of neutron-proton distinguish-ability is offered by a two-component formulation of the exciton model asproposed, for example, by DobeS and BStak [34]. The emission rates, Eq. (13),when used in Eq. (10), satisfactorily reproduce the spectra of nucleons, butsignificantly underpredict the emission of composite particles. For the rates tobe used for alpha particles a review by Gadioli and Gadioli-Erba [35] is con-sulted instead of Eq. (13). An alternative method to deal with cluster emission
452 NOWOTNY and UHL
was developed by Kalbach [32]. In addition to a PE component based ondetailed balance (Eq. (13)), direct reaction contributions, which are calculatedin a very simple statistical way, are taken into account. Recently, Iwamoto andHarada [36] proposed a promising new approach to cluster emission in the frameof the exciton model.
The exciton model described so far does not consider angular momentumand parity. So, if its results are combined in Eq. (9) with those of an HF calculation,one often assumes that PE decay produces for the residual nucleus the same spinand parity distribution as the CN evaporation model. In order to improve thiscrude approximation some authors, such asPlyoko [37], Fu [38, 39] andGruppelaar [40], proposed exciton models which account for angular momentum.
The impact of this improvement is certainly greatest for the productioncross-section of isomers. For the total production cross-sections considered inSec. 4, the errors introduced by neglecting angular momentum and parity willnot in general exceed 30%.
2.3.2. The hybrid model
The hybrid model was proposed by Blann in 1971 [41-43]. It combinesaspects of the simple exciton model and the Harp-Miller-Beine (HME) model[44, 45], which performs a very detailed, and thus relatively complicated, treat-ment of the equilibration process. The resulting expressions are simple and werethe first to predict absolute cross-sections on an a priori basis [46].
The hybrid model is concerned only with the emission of nucleons. Thecross-section (9aQo/9eo) (eQ, e») for emitting a nucleon is given by
(14a)
n=n0
(An = 2)
fi, n) = Z,(e, + Sfi, P, h)
where Zo(eo + So, p, h) represents, for an n-exciton configuration of the compositesystem, the average number of nucleons of the type corresponding to /3 atexcitation energy E = e» + S» so that if such a nucleon is emitted into thecontinuum a channel energy of e» results. The quantities Xc(eg) and A+Ceo) are,respectively, the rates at which such a nucleon is emitted into the continuum orcauses an intranuclear transition, with the creation of an additional particle-holepair. Dn(E) denotes the 'depletion factor' defined in Eq. (11).
Blann et al. [47 ] and Blann and Vonach [18] showed that owing to the propertiesof the nucleon-nucleon cross-section, the quantity Z»(eo + So, p, h) can be
PART 3-1 453
calculated in terms of the particle-hole state densities co(p, h, E) and the singleparticle state density g(eo + So):
i ^ s,) (15)
where XJn) represents the number of particles of the type corresponding to 0.The quantity Xg(n) thus accounts for neutron-proton distinguishability. Theinitial values X^no) and Xy(n0) for protons and neutrons which depend on theprojectile (see Sec. 2.4.3) are increased by 0.5 following each intranucleartransition.
The continuum decay rate Xc(eo) is related to the inverse cross-sectionOa(ea) and the single particle state density g(eR + S«) by
P P P P
The intranuclear transition rates were at first calculated in terms of theaverage nucleon-nucleon cross-section in nuclear matter <a>:
where p is the nuclear density and Vn the velocity of the nucleon under con-sideration. In later developments [46], the rates were also related to the imaginarypart W of the optical potential by X'+(e) = 2W/fi. Because of their radial dependencep(r) and W(r) are averaged over the volume of the nucleus.
An extension of the hybrid model considers explicitly the effects of thenuclear surface region [48]. In this geometry dependent hybrid model, the densityp and the imaginary part W are not averaged over the entire nucleus but over theparticle trajectories in the entrance channel. The latter are defined by the impactparameter Rg = A(C + 1/2), where fl. is the reduced de Broglie wavelength and £the orbital angular momentum. The geometry dependent generalization ofEq. (14a) reads
3a* 2£<* + 1 ) V 6 a ) L£=0 n=n0
(An=2)
where Tg (ea) is the transmission coefficient. The averages of p and W for theindividual contributions Pafe, n, £), which are defined as in Eq. (14b), are
454 NOWOTNY and UHL
calculated in a local density approximation [46]. The two main effects of thesurface region are the reduction of the intranuclear transition rates X\.(eg) dueto the smaller density or the smaller imaginary part of the optical potential andthe limitation of the hole depth due to the reduced Fermi energy. Both effectslead to harder particle emission spectra and thus improve the reproduction ofnucleon induced inelastic scattering and charge exchange reactions.
As the nuclear mean free path is of the order of the nuclear radius, only thefirst collision can be regarded as being localized. Therefore, Eq. (16) is often usedonly for the initial configuration and the contributions to n > n0 are calculatedby means of the geometry independent Eq. (14a). Recently, simple expressionsfor a special type of multiple PE emission were proposed [18]. This effect isexpected to become important for incident energies beyond 50 MeV.
2.4. Auxiliary quantities and model parameters
The models described in the two previous sections require several auxiliaryquantities. These depend on parameters which for the time being have to bedetermined by comparison with appropriate experimental data.
2.4.1. Transmission coefficients
The transmission coefficients for particles are calculated in the frame of theoptical model. In the simplest case, the single channel optical model, they resultfrom solving the scattering problem for a particle in a local complex potentialU(r) = V(r) + i-W(r), which depends on the fragmentation. For a given channelenergy e and each pair of the quantum numbers (£:), where £ is the orbital andj the total angular momentum G = £ + i ), one has to solve the followingequation for the radial wave function Ug:(r):
d2 £(£ +
2 M V S r - V ^ ) + V(r) + iW(r)"e u*J(r) = 0 (17)
The transmission coefficient Tj-(e) is given in terms of the phase shift 5g:(e),by which the asymptotic form of the regular solution of Eq. (17) differs fromthe pure Coulomb scattering wave
Tgj(e) = 1 - |exp[2i68j(e)]|2
Though there currently exist microscopic theories which relate the opticalpotential to the fundamental nucleon-nucleon interaction (see reviews byMahaux [49] and Hodgson [50]), actual calculations of transmission coefficientsemploy phenomenological potentials of the following form:
PART 3-1 455
V ( r ) = - V c f ( r , R c , a c ) + Vso ~ f ( r , R s 0 , a s 0 ) (£ -i) + V C o u l o m b ( r )
W(r) = 4asWs ^ f ( r , Rs, a$) - Wyf(r, R^, av) (18)
f ( r ,R i , a i )={ l+exp[ ( r -R i ) / a i ]} - 1
The real part consists of a central potential of Woods-Saxon form with strengthVc and a spin orbit potential of Thomas form with strength Vs0, while theimaginary part contains a surface peaked and a volume component withrespective strengths of Ws and Wy. The Coulomb potential VC o u ] o m b (r) isassumed to result from a uniformly charged sphere.
The various parameters of a phenomenological potential, i.e. the strengthsVc, Vso , ..., Wv and the geometrical quantities Rc, ac,..., Rv, av, are found bycomparison with appropriate experimental data as cross-sections for elasticscattering and absorption and polarizations. This procedure is described, e.g.,by Hodgson [51 ].
The spin-orbit potential causes the transmission coefficients for particleswith intrinsic spin i to depend on £ and j . If they are used in connection withthe channel coupling scheme described in Sec. 2.2, one has to average T^ withrespect to j :
T = (2£ + 2i+ l)Tg>g + i + (2g + 2 i - l ) T u + i _ n + ... C2|fi-il
Particularly important for cross-section calculations are 'global opticalpotentials', which simultaneously reproduce the relevant data over a wide massand energy region. In general the strengths Vc, Ws and Wy of such potentialsdepend on the incident energy and the nuclear symmetry parameter (N—Z)/A.Information on commonly used global potentials for nucleons, alpha particles,tritons and 3He particles can be found in Ref. [51 ] and in a review article byPerey and Perey [52]. In addition, the global potentials for alpha particles aregiven by Huizenga and Igo [53] and by McFadden and Satchler [54], while forneutrons the potentials given by Rapaport et al. [55] are used.
In general, global optical potentials, when applied for a particular nucleus,will not give as accurate results as a 'local potential' with parameters obtainedfrom data measured for the nucleus of interest or at least for near neighbours.This is particularly true if the energy and/or mass region of the database, onwhich the global potential relies, is exceeded.
The transmission coefficients TXL(e) for photons of multipole type XLare related to the corresponding gamma ray strength function i*XL^e) ^
TX L(e)=27T.e2 L + 1fX L(e)
45 6 NOWOTNY and UHL
Two models for the strength functions are generally used. The Blatt-Weisskopfmodel [56] assumes the strength functions to be energy independent, while theBrink-Axel model [57] relates them to the gamma ray absorption cross-section.The relevant experimental data for the adjustment of the strength functionparameters are in general neutron resonance data and low energy neutroncapture data. For details, see a recent review by Gardner [58].
2.4.2. L evel densities
Most computer codes employ rather simple models which define the leveldensity in terms of a few parameters. The two most popular models are theGilbert-Cameron model [59] and the backshifted Fermi gas model [60]. Bothof them assume the level density to be parity independent: p(E, I, ri)= (l/2)p(E, I), and describe the dependence on the spin I in terms of an energydependent 'spin cut-off parameter' a = a(E):
(I + 1/2)2
p(E,l)=~(2\+\)exp{ — lpo(E) (19)
where po(E) is the total level density as a function of the excitation energy E.The state density o>(E) is related to the total level density by CJ(E) = y/2ira2 p0 (E).
The Gilbert-Cameron model distinguishes two energy regions. For E > Ex ,p0 (E) and a(E) are given by
JPo( '
= Cv 'a(E-P)A2 /3E > Ex (20a)
where a is the 'level density parameter' and P the (tabulated) pairing correction.The original paper [59] proposed that C = 0.0888, while more recent investigationsfavour C = 0.146 [61 ]. In the low energy region E < Ex, the total level densityand a2 are given by
Po(E)=-exp[(E-Eo
E < Ex (20b)o2(E) = o2r
where T is the (nuclear) temperature and Eo is an adjustable constant. Thea parameter of Eq. (20a) is found by reproducing the average resonance spacing,while the quantities Eo, T and Ex are determined by the requirement that po(E),
PART 3-1 457
defined in Eq. (20b), reproduces the cumulative number of low lying levels andsmoothly joins the corresponding expression in Eq. (20a) at E = Ex.
The backshifted Fermi gas model employs only one formula for allexcitation energies:
(21)
a2 (E) = dtAs/3, E ~ A = a t 2 - t
where A represents the 'backshift' and t the (thermodynamic) temperature. Forthe constant d in the definition of a, it is usually assumed that d = 0.0150, a valuewhich corresponds to the rigid body moment of inertia [60]. The parametersa and A are determined by the requirement that Eq. (21) reproduces thecumulative number of low excited levels, as well as the average resonance spacing.
Level density parameters over a wide mass region are tabulated inRefs [59] and [62, 63] for the Gilbert-Cameron model and in Refs [60] and[64] for the backshifted Fermi gas model. These sets can be supplemented orupdated if additional or more recent data on levels and resonances are available.For nuclei with no relevant data, one has to resort to systematics. This may leadto quite inaccurate results - in particular for nuclei far from the line of betastability.
Both phenomenological models consider only in a very rough way theeffects of shell structure and pairing on the energy dependence of the level density.These deficiencies may be overcome by 'microscopic' calculations which arebased on realistic single particle energies and on the BCS model (see Ref. [65]for a recent example). Unfortunately, these calculations are time consuming.In the past few years new, semi-empirical, level density formulas have beenproposed by Kataria et al. [66], Jensen and Sandberg [67] and by Ignatyuk et al.[68]. These formulas parametrize shell effects in terms of the empirical shellcorrection to the nuclear ground state mass. This type of parametrization issimple and seems to be very useful for practical applications as it provides abetter basis for extrapolations to higher excitation energies and to nuclei with noresonance data other than the two phenomenological models described earlier.A recent review by Ramamurthy et al. on these semi-empirical models can befound in Ref. [69].
2.4.3. Pre-equilibrium model parameters
The initial exciton number n0 = p0 + h0 determines the shape of the spectraof the particles emitted in the pre-equilibrium stage. Many investigations haveshown that for nucleon induced reactions n0 has the 'natural' value n0 = 3
458 NOWOTNY and UHL
(p0 = 2, h0 = 1). For the initial numbers X^P) and Xy(3), which are requiredfor the hybrid model (see Eq. (15)), Blann and Vonach propose, for protoninduced reactions,
3N + 2ZX * ( 3 ) = 1 ^ T 7 ~ : X,,(3) = 2-Xff(3) (22a)
and
3Z + 2NX ( 3 ) (22b)
for incident neutrons [18]. These expressions are based on the fact that the(free) n-p cross-section is about three times larger than the (free) n-n and p-pcross-section; the free nucleon-nucleon cross-sections are averaged with respectto the proton and neutron numbers Z and N of the target nucleus.
For composite projectiles the choice of (p0, h0) is less obvious and oftennot unique. We quote as typical examples some results. Exciton modelcalculations for incident alpha particles and 3He particles required (p0 = 5 ,h0 = 1) [32] and (p0 = 3, h0 = 1) [70], respectively. Successful applications ofthe hybrid model for alpha induced reactions were reported with n0 = 4 andXff(4) = Xj/4) = 2 [71-73]. For incident 3He particles, Chevarier et al. reportedhybrid model calculations with n0 = 4 and Xw(4) = Xv(4) = 2 or [Xn(4) - 2.5,Xj,(4) = 1.5] [74], whereas Misaelides and Miinzel used n0 = 5 and [Xff(5) = 2.5,Xj,(5) =1.5] [73]. Deuteron induced reactions were analysed by Jahn et al. inthe framework of the hybrid model with n0 = 3 or n0 = 2 [75].
In addition to the problem of the choice of the initial exciton number, theanalysis of composite, particle induced reactions by pre-equilibrium models iscomplicated by the presence of a breakup component in the particle emissionspectra which is not accounted for by these models. This holds, in particular,for weakly bound projectiles such as deuterons or 3He particles and higherincident energies.
For the particle-hole state densities, which are required for the exciton andthe hybrid model as well, the following most commonly used expression wasderived by Williams:
g [ g E - ( p 2 + h 2 + p - 3 h ) / 4 ] P + h - 1
CJ(P, h, E) =
under the assumption of an energy independent, single particle state density g[76].The quantity g may be related to the a parameter of the phenomenological leveldensity models of Sec. 2.4.2 by g = (6/7T2)a. Very often the value g = A/13,corresponding to a = A/8, is employed where A is the mass number.
PART 3-1 459
In later developments, Williams' formula was corrected for several effects:finite depth of the potential well, which restricts the excitation energy of theholes and pairing, shell effects and long range energy variations. For details seeKalbach's recent review, which also surveys the calculation of the quantitywAn(n,E)ofEq. (12) [77].
The particle-hole creation rates A'+(n, E) of the exciton model, which arebased on the 'golden rule', Eq. (12), require the average squared matrix element|M|2. By analysis of appropriate experimental data, Kalbach-Cline [78] foundfor the dependence of this quantity on mass number A and excitation energy Ethat
|M|2(E) = KA-3E-1 (23)
The numerical value of the constant K critically depends on the expression usedfor the particle emission rates. For g = A/13 and for the emission rates proposedby Kalbach in Ref. [32], K = 400 MeV3. In order to reproduce the morerealistic energy and exciton number dependence of the tabulated rates A'+(n, E),which were obtained by Gadioli et al. [30] on the basis of the nucleon-nucleoncross-section in nuclear matter, Kalbach proposed the following relations:
)A3e V 7 MeV
, for 2 MeV < e < 7 MeV
K' , for 7 MeV < e < 15 MeV
A3e
K' / ! 5 M e V y 2 , f o r l 5 M e V < e
A3e
where e = E/n and the constant K' assumes the value 135 MeV3 under theconditions specified for Eq. (23) [79].
The intranuclear transition rates X1+(e) for the hybrid model, which of course
are conceptually different from the exciton model rates A^.(n, E) are either basedon the expressions for the Pauli-corrected nucleon-nucleon cross-section, givenby Kikuchi and Kawai [80], or on the global optical potentials for nucleons byBecchetti and Greenlees [81 ]. In the latter case, the rates should not be used forenergies much greater than 55 MeV, corresponding to the upper energy limit of
460 NOWOTNY and UHL
the potentials. For the radial dependence of the nuclear density which is requiredfor the geometry dependent effects, and for further details, see the recent paperby Blann and Vonach [18].
3. COMPUTER CODES
Over the past few years many computer codes have been developed whichcalculate nuclear reaction cross-sections on the basis of a combination ofequilibrium and pre-equilibrium models. In this section, we briefly describe somerepresentative programs and discuss their applicability for the calculation ofactivation product cross-sections. A more detailed discussion of a larger numberof codes can be found in a recent review by Uhl [82].
Alice/Livermore 82 is the most recent version of the widely used Alicecodes developed by Blann and Bisplinghoff [83]. The program calculates, forarbitrary projectiles and emitted particles selected among neutrons, protons,alpha particles and deuterons (the actual choices are n; n and p; n, p and a;n, p, a and d), the activation product cross-sections for all nuclei of a rectanglein the (Z, N) plane which may be 11 mass units wide and 9 charge units deep.
A WE calculation is performed for the CN evaporation contribution. Thes-wave approximation may be used as an option; in that case the yrast level iscalculated by either assuming a rigid rotor or by means of the equilibriumdeformed, rotating liquid drop model of Cohen et al. [84]. Pre-equilibriumemission of nucleons is treated within the framework of either the hybrid orthe geometry dependent hybrid models. A simple formalism for multiplePE emission [18] is included. The most recent version of the code also allows,optionally, for isospin effects in precompound decay.
The Alice/Livermore 82 code is ideally suited for fast calculations ofactivation product cross-sections. Owing to many built-in data — as, for example,nuclear masses and parameters for global optical potentials — and, owing toconvenient default options, the input is short and easy to prepare. The choiceof the default parameters for PE decay is discussed by Blann and Vonach [18].The running time of the code is short, especially if the inverse cross-sectionsare calculated not by the optical model routines but by the sharp cut-offalgorithm [85], or are supplied as inputs. The only restrictions on the use ofAlice/Livermore 82 are: reactions with first chance emitted composite particles(since for those ejectiles no PE contribution is considered) and the limitationsinherent in the WE method of calculation (see Sec. 2.2).
In the following, we discuss the application of codes which allow for angularmomentum and parity conservation and include gamma ray cascades. ForHF calculations, the spectrum of excited states of all residual nuclei is dividedinto low lying known levels and a 'continuum' region described by a level densityformula. The gamma ray branching ratios for the transitions between these
PART 3-1 461
levels are required for the calculation of isomeric state populations. Thus, owingto the extensive information on the level schemes of many nuclei, HF codesdemand much more input data than WE codes. Since angular momentum dependentcalculations require much more time and storage, HF codes in general do notsimultaneously calculate activation product cross-sections for as many final nucleias, for example, does Alice/Livermore 82.
An extreme example of the restriction of the number of product nuclei isthe code known as Stapre which calculates, for up to six sequentially emittedparticles (selected among n, p, a and d) in addition to other quantities, theproduction cross-sections for all nuclei lying on one 'reaction path' [13]. Such apath is defined by a specific sequence of emitted particles, e.g. (apnn). Whilethis restriction is irrelevant for reactions such as (p, nn), problems arise if the finalnucleus of interest is populated by several paths as, for example, for the (p, np),(p, pn) and (p,d) reactions. In that case several different runs are required forthe final results. This disadvantage is at least partly overcome by the programGnash by Young and Arthur [86]. In this code the ejectiles may be chosenamong n, p, a, d, t and 3He. Activation product cross-sections for up to tendifferent final nuclei can be calculated and contributions of different paths areobtained in one run. Nevertheless, the maximum number of final nuclei is muchsmaller than for Alice/Livermore 82. The PE contribution in Stapre and Gnashis calculated within the framework of the exciton model. While Stapre employsfor alpha emission the model of preformed alpha particles by Milazzo-Colli andBraga-Marcazzan [87, 88] Gnash uses for pre-equilibrium emission of compositeparticles the simple statistical direct reaction contributions proposed byKalbach [32], in addition to the results based on detailed balance.
Finally, there is the program TNG1 by Fu which, in contrast to the twoaforementioned HF codes, performs an angular momentum dependent treatmentof the PE contribution in the framework of the exciton model [38, 39]. It isof special interest for isomeric state populations in cases of a dominant PEcontribution. TNG1 handles reactions with up to three emitted particles.
Among the codes mentioned in this section all but TNG1 account forfission. Thus they can also calculate activation product cross-sections in caseswhere fission competition is relevant.
4. APPLICATIONS
Thus far the codes Overlaid Alice [89] and, later, its version Alice/Livermore 82[83], as well as Stapre [13] have been used for the calculation of activation productcross-sections. For practical purposes the Alice codes are preferred as only fewinput data are required and the computer execution times are moderate incomparison with Stapre. Indeed, Stapre might yield the more accurate results,as is shown below.
462 NOWOTNY and UHL
In the following are given some results obtained with Alice to demonstratethe accuracy of calculated excitation functions. All calculations were done underthe same assumptions to maintain an a priori character, i.e. the input parameterswere not varied to obtain better agreement between experimental data andtheoretical results. In all cases an evaporation calculation with multiparticleemission according to the statistical model was chosen. The default optical modelsubroutine was used for the calculation of the inverse cross-sections. Forpre-compound emission of nucleons the geometry dependent hybrid model was chosen.
Reaction Q-valuesand binding energies were taken first from Ref. [90], butlater the Myers-Swiatecki mass formula [91 ] was used which is available as thedefault option in the code. In the most recent version an option exists to use asmuch experimental mass data as are available. In addition, the number of nucleiof each Z and the number of elements to be included in the calculation can bespecified. For each projectile energy the cross-sections for the evaporation cascadeleading from the composite nucleus to the final nuclei, as defined above, arecalculated.
4.1. Proton induced reactions
An important input parameter for pre-equilibrium decay which depends onthe projectile is the initial number of excitons (see Sec. 2.4.3). For protoninduced reactions the initial number of excited protons and neutrons was takenas 1.25 and 0.75, respectively. These initial exciton numbers are obtained fromexpressions (22a) and (22b) under the assumption that N = Z. Together withone hole, this gives a total of three excitons [92]. To demonstrate the simpleinputs required for Alice, a sample input for the 68Zn(p, xn) + 68Zn(p, pxn)reactions is listed below (without regard to the input format required by Alice):
- Projectile mass number (AP) = 1.- Target mass number (AT) = 68.- Projectile charge (ZP) = 1.- Target charge (ZT) = 30.- Number of product nuclei of each Z (NA) = 4 to include (p, 3n) reactions.- Number of Z of product nuclei (NZ) = 2 to include (p, pxn) reactions.- Mass option (MC) = 0 for the Myers-Swiatecki mass formula or (MC) = 10
to include experimental mass data, if available.- Number and types of particles to be emitted from each nuclide (M3) = 3
for p, n and alphas.- Pairing option for the mass formula (MP) = 3 for normal pairing shift.
For each projectile energy the following input has to be supplied:
- Projectile kinetic energy (EQ), in MeV.- Type of calculation (JCAL) = 1 for the Weisskopf-Ewing evaporation
calculation.
PART 3-1 463
- Initial exciton number (particles and holes) (TD) = 3.- Initial excited neutron number (EX1) = 0.75.- Initial excited proton number (EX2) = 1.25.- Pre-equilibrium model (TMX) = 1 for the geometry dependent hybrid model.- Intranuclear transition rates (AV) = 0 for optical model transition rates.
If E > 55 MeV, then (AV) = 1 for nucleon-nucleon mean free paths.
With this input configuration and a calculation of activation cross-sectionsfor 18 projectile energies from 6 to 36 MeV, the CPU time on a Control DataCorporation Cyber 170-720 is about 270 s. Two similar runs for 66Zn and 67Znas target nuclei are sufficient to yield the relevant figures for estimating theexcitation functions and production yields for natZn(p, xn)67Ga and itscontaminants. A reduction in CPU time is possible by computing the inversereaction cross-sections with a classical sharp cut-off model, though this optionwas not tested.
In the following, a few examples of excitation functions are given whichare of interest for the production of radio isotopes used in nuclear medicine.
4.1.1. 61Ga
In spite of the fact that 57Ga has been widely used in nuclear medicine,only a small quantity of experimental data on the excitation functions of protonson zinc targets is available. The principal radionuclidic impurity, due to its half-life of 9.5 h, is 66Ga. Figures 1-5 show the results of the calculations comparedwith data from the literature [93-95] for reactions with 66Zn, 67Zn and 68Zn astarget nuclei to be considered here. The most comprehensive data have beenpublished by Little and Lagunas-Solar [95]. In comparison with these data,calculated curves show a steeper rise and, in some cases, less agreement for thepre-equilibrium tail. Unfortunately, the energy errors are not given and it shouldbe remembered that the excitation function curves were obtained from compositeyield curves for a natZn target taking into account Q-values and general reactioncharacteristics [95] which might result in less reliable data for the tail. Agreementin maximum cross-section is better than 20%.
4.1.2. inKr
This radioisotope has been of interest as the precursor of 77Br, but the noblegas can be used directly, being a positron emitter in positron emission tomography.The essential contaminant for proton induced reactions with bromine is 76Kr.The calculated cross-sections for reactions with natural bromine are shown inFigs 6 and 7. Obviously the excitation functions from Lundqvist et al. [96] arenot in agreement with either other experimental or with calculated data. Forthe reaction product 77Kr, agreement is fairly good for data from DeJong et al. [97]
464 NOWOTNY and UHL
10 F
10' -
10' -
/ ' \
T11111t
1
111
. . . l . i . . . .
66 ZnCp. rO^Ga
\ ~ ~ ~ - - - -
• .
Ref. [94]Ref. [95]
1 . . . . 1 . . . .
10 20 30 40(MeV)
FIG. 1. Calculated and experimental excitation functions for66'Zn(p, n )66'Ga. Error barsindicate typical experimental errors, if quoted. For clarity, individual measured cross-sectionsare not shown. Cross-section data by Little and Lagunas-Solar [95] have been obtained by theauthors from composite yield curves for a natural zinc target.
10"
10'
10"
Zn(p. n)6 7Go
AliceRef. [95)
10 4020 30Ep (MeV)
FIG. 2. Calculated and experimental excitation functions for 67Zn (p, n)67Ga (for commentssee Fig. 1).
- 3
0
FIG. 3. Same as Fig. 1, but for elZn(p, 2n)66Ga.
20 30Ep (MeV)
PART 3-1 465
iff"
10'
10'
10"
68Zn(p.2n)ff7Ga
AliceRef. [931Ref. [95)
10 20 30 40E (MeV)
FIG. 4. Same as Fig. 1, but for 6SZn (p, 2n)61Ga.
10 20 30Ep (MeV)
FIG. 5. Same as Fig. 1, but for 6iZn(p, 3n)(AGa.
Iff*
10 -
10' -
io:
40
•
• 1
j
{//IIIj
" " Br (p. xn) 77Kr
Ref. [97]Ref. [96]Ref. [99]Ref. [98)Ref. (100)
30 40 70SO 60Ep (MeV)
FIG. 6. Calculated and experimental cross-sections for proton induced reactions with naturalbromine leading to 71Kr. The data from Dikiic et al. [100], for reactions with 19Br and SiBr,were combined to obtain the effective cross-section.
466 NOWOTNY and UHL
10'
10'
10.
"•"BrCp. xn) 7sKr
AliceRef. [96)Ref. [98]Ref. [97]Ref. [100]Ref. [99]
70'20 30
FIG. 7. Calculated and experimental excitation functions for n3tBr(p, xn)16Kr (see also Fig. 6).
40 SO 60Cp (MeV)
10'
10'
l27 \ (p. n)
AliceStapreRef. [103]
10 20 30E p (MeV)
FIG. 8. Experimental excitation function for 12'!I(p, nj 121Xe, together with cross-sectionscalculated by the Alice and Stapre codes [102].
and Nozaki et al. [98]; with respect to the data from Weinreich and Knieper onlythe shape is reproduced [99]. Data from DikSic et al. [100] are in less agreement.For the final nucleus 76Kr (which can be considered to be far away from thestability line) characteristics of the excitation function are similar, but dis-crepancies exist in the maximum cross-section up to a factor of 2.7.
4.1.3. niXe
This radioisotope exhibits some advantages when compared with 133Xe andis suitable for use in nuclear medicine, though it has not attracted widespread
PART 3-1 467
interest [101 ]. The results for the reaction 127I(p,n) 127Xe (Fig. 8) also includedata calculated using Stapre [102]. The Stapre data match the experimentalresults from Colle and Kishore [103] over the entire energy range. For theAlice curve only the initial rise until the maximum cross-section is in excellentagreement, but the tail of the excitation function is less satisfactorily reproduced.There exists no plausible reason for the excitation function rising again after theinitial peak, but to preserve the a priori character we have not varied the inputparameters.
10
IO1
10'
AliceRef. [104)Ref. (105)Ref. [106)Ref. [107 JRef. [96)
40 50 60 70Ep (MeV)
FIG. 9. Calculated and experimental excitation functions for niI(p, 5n) l23Xe.
10s
10"
10'
10'40
U7 I (p. 3n>
" " ! - - - _
AliceRef. [104]Ref. [105]Ref. (106)Ref. [107]Ref. [96]
SO 60Ep (MeV)
70
FIG. 10. Calculated and experimental excitation functions for the production of the contami-nant 125I via 121I(p, 3n) 125Xe -* 12SI, shown for the same energy window as in Fig. 9.
468 NOWOTNY and UHL
10'-
10 -
10' -
10'
• 1
""'THp.x^^Pb
Ref. [109]Ref. [110]
10 20 30 40 50
FIG. 11. Effective cross-sections for proton induced reactions with natural thallium producing203Pb.
10'
10*
10"
10'10
eTKp.xn> ^"Pb
AliceRef. [108)Ref. [109]Ref. [110]
30 40(MeV)
50
FIG. 12. Same as Fig. 11, but for production of 201Pb.
PART 3-1 469
10'
10'
10'
ltf 10
AliceRef. |109lRef. [110]
30 40Ep (MeVI
SO
FIG. 13. Same as Fig. 11, but for production of200Pb.
4.1.4. 123Xe
The introduction of 123I as a substitute for 131I has been of great importance.The quality of scintigraphic examinations has been improved, with concurrentreduction in patient dose. The production of 123Xe as the precursor of )23I is thebest method to obtain high radionuclidic purity. Any other direct production bybombardment of Te or Sb targets suffers from contamination by 124I, whichboth impairs scintigraphic properties and increases radiation dose. Unfortunately,the proton energies required for the 127I(p, 5n) 123Xe reaction are too high forapplication with compact cyclotrons. The only impurity produced is 12SI, butsetting an appropriate energy window for the (p, 5n) reaction and half-life dis-crimination of 12SXe both give relatively low 125I activities.
The calculated excitation functions are given in Figs 9 and 10. Taking intoaccount the discrepancies between the various experimental data [96, 104-107],the agreement is fair for both reactions.
4.1.5. 20lPb
2O1T1 is widely used for myocardial studies. It can be produced with a highdegree of purity via its precursor 20IPb by bombarding natural thallium targetswith protons. 203Pb is also produced in this way and has generated some medicalinterest (see, for example, citations in Ref. [110]). The calculated excitation
470 NOWOTNY and UHL
10'
10
FIG. 14. Comparison of calculated radioisotope production yields, Y.aic, with data from litera-ture, Y^ (see Ref. [5]). Dashed lines indicate a deviation by a factor of 2 from equality(1 curie = 3.70 X 1010 Bq).
functions for proton induced reactions leading to 200Pb, 201Pb and 203Pb areshown in Figs 11-13. Only the contribution due to 203Tl(p, n) 203Pb has notbeen included. Agreement between experimental [108-110] and calculated datais good. Again, the reproduction of the pre-equilibrium tail of the 20STl(p, 3n) 203Pbreaction is less satisfactory.
4.2. Yield calculations
To check the usefulness of the theoretical excitation functions for protoninduced reactions, yield figures were calculated according to the conditions citedin the literature and then compared with the respective yield data quoted therein.Yield figures in the literature comprise experimental yields and yields calculatedfrom yield functions or excitation functions. Figure 14 shows a comparisonbetween calculated yields and yields reported in the literature.
It was found that in general the literature yield data can be reproduced bycalculated yields to within a factor of 2. It must be remembered that all of theexperimental errors, which are often not quoted, are also included in thiscomparison. Further, there remain hidden many factors in the various methodsby which the yield figures are obtained. No definite trend in an over- or under-estimation of the data in the literature could be noted. The proton energy coversa range of up to 70 MeV and target nuclei with Z > 15 are included.
PART 3-1 471
10 20 30 40 SO BO 70 80 90
FIG. 15. Excitation functions for (d, xn) reactions with natural bromine from Qaim et al [111 ]and calculated using Alice ( j .
0 10 20 30 40 SO 60 70 80 90
FIG. 16. Same as Fig. 15, but for nitBr(d, pxn)17Br.reactions.
4.3. Reactions with particles other than protons
Several excitation functions for deuteron and 3He induced reactions havebeen calculated using Alice, with the same input considerations as mentionedabove except for the initial exciton configuration. The efforts to reproduceexcitation functions and particle spectra require exciton numbers which do notalways conform to the initial physical concept (see Sec. 2.4.3). For deuteronstotal exciton numbers of 2 (1 neutron, 1 proton, 0 holes) or 3 (2 neutrons,1 proton, 0 holes) have given the best results. In general, the discrepancies aregreater than for proton induced reactions. Two examples are given to demonstratethe usefulness of a priori calculations.
472 NOWOTNY and UHL
SO
FIG. 17. Excitation functions for 12'7fd, xnj reactions from Weinreich et al. [112]( ) andcalculated using Alice ( ).
60 70 eo goE d (MeV)
FIG. 18. Same as Fig. 17, but for I(d, pxn) reactions.
The production of 77Kr can also be accomplished by deuteron bombardmentof bromine targets. Experimental excitation functions from Qaim et al. [ I l l ]and the calculated total cross-sections obtained with an initial exciton numberof 2 are shown in Figs 15 and 16. While (d, xn) reactions are overestimated byAlice, the (d, pxn) cross-sections are too low.
The situation for the production of )23Xe via the 127I(d, 6n) reaction, togetherwith other companion reactions, is shown in Figs 17 and 18. It can also be seenthat the discrepancies with the experimental data from Weinreich et al. [112]are larger than those for proton induced reactions. Michel and Galas [113] havereported good agreement between calculated and experimental data for a numberof deuteron induced reactions with s9Co when using exciton numbers of 2 or 3.
PART 3-1 473
For other projectiles, e.g. 3He, the situation is even less satisfactory and theappropriate choice of initial exciton numbers for an a priori calculation is notobvious (see Sec. 2.4.3).
5. CONCLUSIONS
The applicability of the codes described is limited by several factors. Ingeneral one can assume that the parameter sets make feasible a calculation formasses A > 30, but results for lighter nuclei have also shown satisfactory agree-ment of cross-sections. Calculations based on the optical model and the compoundnucleus evaporation model for neutron induced reactions on biologically interestingelements with A > 12 (carbon, nitrogen and oxygen) have been performed forneutron energies from 20 to 50 MeV by Dimbylow [114]. Indeed, the fewexperimental data available have been used for a data fit so that the results werenot truly obtained for a priori conditions.
Further, reproduction of activation cross-sections will get worse for productnuclei far away from the stability line for beta decay. The particle energiesavailable in production facilities rarely exceed proton energies of perhaps 70 MeV,but compact cyclotrons frequently used for these purposes produce protons ofup to about 45 MeV. For this energy range the nuclear models used in thesecodes should be adequate.
The results of calculations for nucleon induced reactions generally showbetter agreement than for reactions involving 'complex' particles (deuterons,3He, alpha particles) in the entrance and/or exit channels. In particular, theemission of these particles during pre-equilibrium decay is not accounted forby the Alice code.
It must be stressed that it is difficult to give figures on the accuracy ofcalculated excitation functions. In particular, during the initial rise the cross-sections could differ by large factors and it is this section of the excitationfunction which is usually affected most by uncertainties in projectile energy.Using the Alice code for proton induced reactions, with input parameters asgiven in Sec. 4.1, it was shown that the yield figures obtained from calculatedcross-sections differ in general by less than a factor of 2 for all calculations beingmade under the same a priori conditions, without any adjustment of the inputparameters. This uncertainty comprises all experimental errors in the deter-mination of the yield. The comparison also indicates that there is no systematicover- or underestimation of production yield by calculated yields. If experimentaldata for a reaction under investigation are missing it would be useful to study somereactions on neighbouring target nuclei if possible. In this way it is possible to gainexperience of the predictive power in that mass region.
An individual selection of input parameters according to nuclear dataavailable for a specific mass region or by experience could perhaps give better
474 NOWOTNY and UHL
agreement. This is particularly true of the choice of exciton numbers forcomposite projectiles. For deuteron induced reactions the preferable configu-ration seems to be either two or three initial excitons (see also Refs [75. 113]).So far, the experience shows that agreement with experimental data is lesssatisfactory than for nucleon induced reactions. For 3He and alpha projectileswe still have to gain experience to assess the practicability of 'global' initialexciton numbers for a priori calculations.
Setting up the input parameters for the Alice code requires little time. Themost recent version, Alice/Livermore 82, has undergone some revisions. However,most of the results shown in this contribution have been obtained using its earlierversion, Overlaid Alice, so that new results could be somewhat different, thoughin all cases where calculations for a particular reaction were made with bothcodes, negligible differences in activation cross-sections were found. Nuclear datafiles, e.g. for inverse cross-sections, level density parameters and masses couldbe useful in saving computer time and helpful in improving the accuracy of theresults.
An assessment of the advantages and limitations of various productionmethods by means of a priori calculations seems feasible for proton inducedreactions. It is not suggested that one should rely only on calculated excitationfunctions, but in the planning of new production methods calculated activationcross-section data could be helpful.
REFERENCES
[ l] KELLER, K.A., LANGE, J., MUNZEL, H., PFENNING, G., Excitation Functions forCharged Particle Induced Nuclear Reactions (Landolt-Bornstein New Series Group I),Vol. 5b, Springer-Verlag, Berlin (West) (1973).
[2] The Bibliography of Integral Charged Particle Nuclear Data, 4th edn (BURROWS, T.W.,DEMPSEY, P., Eds), Brookhaven National Lab., Upton, NY, Rep. BNL-NCS-50640 (1980).
[3] KELLER, K.A., LANGE, J., MUNZEL, H., Estimation of Unknown Excitation Functionsand Thick Target Yields for p, d, 3He and Alpha Reactions (Landolt-Bornstein New SeriesGroup I), Vol. 5c, Springer-Verlag, Berlin (West) (1973).
[4] QAIM, S.M., Radiochim. Acta 30 (1982) 147.[5] NOWOTNY, R., Int. J. Appl. Radiat. Isot. 32 (1981) 73.[6] AUSTERN, N., Direct Nuclear Reaction Theories, Wiley, New York (1970).[7] BOHR, N., Nature (London) 137 (1936) 344.[8] WEISSKOPF, V.F., EWING, D.H., Phys. Rev. 57 (1940) 472.[9] HAUSER, W., FESHBACH, H., Phys. Rev. 87 (1952) 366.
[10] VOGT, E., in Advances in Nuclear Physics I (BARANGER, M., VOGT, E., Eds), PlenumPress, New York (1968) 261.
[11] MOLDAUER, P.A., "Statistical theory of neutron nuclear reactions", Nuclear Theory forApplications (Proc. Winter Course Trieste, 1978), IAEA-SMR-43, IAEA, Vienna (1980) 165.
[12] MAHAUX, C, WEIDENMULLER, H.A., Annu. Rev. Nucl. Part. Sci. 29 (1979) 1.
PART 3-1 475
[13] STROHMAIER, B., UHL, M., "STAPRE - A statistical model code with consideration ofpre-equilibrium decay", Nuclear Theory for Applications (Proc. Winter Course Trieste,1978),IAEA-SMR-43, IAEA, Vienna (1980) 313.
[14] GROVER, J., Phys. Rev. 123 (1961) 267.[15] STENGL, G., UHL, M., VONACH, H., Nucl. Phys. A290 (1977) 109.[16] BLANN, M., MERKEL, G., Phys. Rev. 137B (1965) 367.[17] LANE, A.M., Phys. Rev. C 18(1978) 1525.[18] BLANN, M., VONACH, H., Phys. Rev. C 28 (1983) 1475.[19] AGASSI, D., WEIDENMULLER, H.A., MANTZOURANIS, G., Phys. Lett. 22 (1975) 145.[20] FESHBACH, H., KERMANN, A.K., KOONIN, S.E., Ann. Phys. (N.Y.) 125 (1980) 429.[21] TAMURA, T., UDAGAWA, T., LENSKE, H., Phys. Rev. C 26 (1982) 379.[22] GRIFFIN, J.J., Phys. Lett. 17 (1966) 478.[23] GRIFFIN, J.J., Phys. Lett. 24B (1967) 5.[24] CLINE, C, BLANN, M., Nucl. Phys. A172 (1971) 225.[25] UHL, M., "Computer calculations of neutron cross sections and gamma-cascades with the
statistical model with consideration of angular momentum and parity conservation",Nuclear Theory in Neutron Nuclear Data Evaluation (Proc. Consultants Meeting Trieste,1975), Vol. 2, IAEA-190, IAEA, Vienna (1976) 361.
[26] AKKERMANS, J.M., GRUPPELAAR, H., Z. Phys. A300 (1981) 345.[27] WILLIAMS, F.C., Jr., Phys. Lett. 31B (1970) 184.[28] OBLoflNSKY, P., RIBUNSKY, I., BE"TAK, E., Nucl. Phys. A226 (1974) 347.[29] GADIOLI, E., GADIOLI-ERBA, E., TAGLIAFERRI, G., Nucl. Phys. A217 (1973) 589.[30] GADIOLI, E., GADIOLI-ERBA, E., HOGAN, J.J., Phys. Rev. C 16 (1977) 1404.[31] CLINE, C.K., Nucl. Phys. A193 (1972) 417.[32] KALBACH, C, Z. Phys. A283 (1977) 401.[33] BIRRATARI, C, et al., Nucl. Phys. A201 (1973) 579.[34] DOBES, J., BETAK, E., in Neutron Induced Reactions (Proc. Europhysics Topical Conf.
Smolenice, 1982) (OBLOZINSKY, P., Ed.), Czechoslovak Academy of Sciences, Bratislava(1982).
[35] GADIOLI, E., GADIOLI-ERBA, E., "Recent results in the theoretical description ofpre-equilibrium processes", Nuclear Theory for Applications — 1980 (Proc. InterregionalAdvanced Training Course Trieste, 1980), Vol. 1, IAEA-SMR-68, IAEA, Vienna (1980) 3.
[36] IWAMOTO, A., HARADA, K., Phys. Rev. C 26 (1982) 1821.[37] PLYOKO, V.A., Sov. J. Nucl. Phys. 27 (1978) 623.[38] FU, C.Y., "Development and applications of multi-step Hauser-Feshbach/pre-equilibrium
model theory", Nuclear Theory for Applications - 1980 (Proc. Interregional AdvancedTraining Course Trieste, 1980), Vol. 1, IAEA-SMR-68, IAEA, Vienna (1980) 35.
[39] FU, C.Y., Oak Ridge National Lab., TN, Rep. ORNL/TM-7042 (1980).[40] GRUPPELAAR, H., in Basic and Applied Problems of Nuclear Level Densities (Proc.
IAEA Advisory Group Meeting Brookhaven, 1983) (BHAT, M.R., Ed.), BrookhavenNational Lab., Upton, NY, Rep. BNL-NCS-51694 (1983) 143.
[41] BLANN, M., Phys. Rev. Lett. 27 (1971) 337.[42] BLANN, M., Phys. Rev. Lett. 27 (1971) 700E.[43] BLANN, M., Phys. Rev. Lett. 27 (1971) 155OE.[44] HARP, G.D., MILLER, J.M., BEINE, B.J., Phys. Rev. 165 (1968) 1166.[45] HARP, G.D., MILLER, J.M., Phys. Rev. C 3 (1971) 1847.[46] BLANN, M., Nucl. Phys. A213 (1973) 570.[47] BLANN, M., MIGNEREY, A., SCOBEL, W., Nukleonika 21 (1976)335.[48] BLANN, M., Phys. Rev. Lett. 28 (1972) 757.
47 6 NOWOTNY and UHL
[49] MAHAUX, C, "Theoretical aspects of the optical model", Nuclear Theory for Applications(Proc. Winter Course Trieste, 1978), IAEA-SMR-43, IAEA, Vienna (1980) 97.
[50] HODGSON, P.E., in Nuclear Physics (Proc. 6th Symp. Oaxtepec, Mexico, 1983),CONF-830138(1983).
[51] HODGSON, P.E., Nuclear Reactions and Nuclear Structure, Clarendon Press, Oxford (1971).[52] PEREY, CM., PEREY, F.G., At. Nucl. Data Tables 17 (1976) 1.[53] HUIZENGA, J.R., IGO, G.J., Argonne National Lab., IL, Rep. ANL-6373 (1961).[54] McFADDEN, L., SATCHLER, G.R., Nucl. Phys. 84 (1966) 177.[55] RAPAPORT, J., KULKARNJ, V., FINLAY, R.W., Nucl. Phys. A330 (1979) 15.[56] BLATT, J.M., WEISSKOPF, V.F., Theoretical Nuclear Physics, Wiley, New York (1952).[57] AXEL, P., Phys. Rev. 126 (1962) 671.[58] GARDNER, D.G., in Fast Neutron Capture Cross Sections (Proc. NEANDC/NEACRP
Specialists Meeting Argonne, Illinois, 1982) (SMITH, A.B., POENITZ, W.P., Eds),Argonne National Lab., IL, Rep. ANL-83-4 (1982) 67.
[59] GILBERT, A., CAMERON, A.G.W., Can. J. Phys. 43 (1965) 1446.[60] VONACH, H., HILLE, M., Nucl. Phys. A217 (1969) 289.[61] REFFO, G., Comitato Nazionale per l'Energia Nucleare, Rome, Rep. CNEN-RT/FK78) 11
(1978).[62] ROSE, E.K., COOK, J.L., Australian Atomic Energy Commission Research Establishment,
Lucas Heights, Rep. AAEC/E419 (1977).[63] COOK, J.L., ROSE, E.K., in Nuclear Data for Science and Technology (Proc. Int. Conf.
Antwerp, 1982) (BoCKHOFF, K.H., Ed.), Reidel, Dordrecht (1983) 805.[64] DILG, W., SCHANTL, W.; VONACH, H., UHL, M., Nucl. Phys. A217 (1973) 269.[65] MAINO, G., MENAPACE, E., VENTURA, A., Nuovo Cimento S7A (1980) 427.[66] KATARIA, S.K., RAMAMURTHY, V.S., KAPOOR, S.S., Phys. Rev. C 18 (1978) 549.[67] JENSEN, A.S., SANDBERG, J., Phys. Scr. 17 (1978) 107.[68] IGNATYUK, A.V., ISTEKOV, K.K., SMIRENKIN, G.N., Sov. J. Nucl. Phys. 29 (1979)
450.[69] RAMAMURTHY, V.S., KATARIA, S.K., KAPOOR, S.S., in Basic and Applied Problems
of Nuclear Level Densities (Proc. IAEA Advisory Group Meeting Brookhaven, 1983)(BHAT, M.R., Ed.), Brookhaven National Lab., Upton, NY, Rep. BNL-NCS-51694(1983) 187.
[70] GRIMES, S.M., ANDERSON, J.D., McCLURE, J.W., POHL, B.A., WONG, C, Phys.Rev. C 5 (1972) 830.
[71] BLANN, M., MIGNEREY, A., Nucl. Phys. A186 (1972) 245.[72] CHEVARIER, A., CHEVARIER, N., DEMEYER, A., HOLLINGER, G., PERTOSA, B.,
TRAN, M.D., Phys. Rev. C 8 (1973) 2155.[73] MISAELIDES, P., MUNZEL, H., J. Inorg. Nucl. Chem. 42 (1979) 937.[74] CHEVARIER, A., et al., Nucl. Phys. A231 (1974) 64.[75] JAHN, P., PROBST, H.-J., DJALOEIS, A., DAVIDSON, W.F., MAYER-BORICKE, C,
Nucl. Phys. A209 (1973) 333.[76] WILLIAMS, F.C., Jr., Nucl. Phys. A166 (1971) 231.[77] KALBACH, C, in Basic and Applied Problems of Nuclear Level Densities (Proc. IAEA
Advisory Group Meeting Brookhaven, 1983) (BHAT, M.R., Ed.), Brookhaven NationalLab., Upton, NY, Rep. BNL-NCS-51694 (1983) 113.
[78] KALBACH-CLINE, D., Nucl. Phys. A210 (1973) 590.[79] KALBACH, C, Z. Phys. A287 (1978) 319.[80] KIKUCHI, K., KAWAI, M., Nuclear Matter and Nuclear Interactions, North-Holland,
Amsterdam (1968).[81] BECCHETTI, F.D., GREENLEES, G.W., Phys. Rev. 182 (1969) 1190.
PART 3-1 477
[82] UHL, M., "Recent advances in nuclear model code developments", Nuclear Theory forApplications - 1982 (Proc. Winter Course Trieste, 1982), IAEA-SMR-93, IAEA, Vienna(1982)5.
[83] BLANN, M., BISPUNGHOFF, J., Lawrence Livermore Lab., Livermore, CA, Rep.UCID-19614(1982).
[84] COHEN, S., PLASIL, F., SWIATECKI, W.J., Ann. Phys. (N.Y.) 82 (1974) 557.[85] BLANN, M., Phys. Rev. C 21 (1980) 1770.[86] YOUNG, P.G., ARTHUR, E.D., Los Alamos Scientific Lab., NM, Rep. LA-6947 (1977).[87] MILAZZO-COLLI, L., BRAGA-MARCAZZAN, G.M., Phys. Lett. B38 (1972) 155.[88] MILAZZO-COLLI, L., BRAGA-MARCAZZAN, G.M., Nucl. Phys. A210 (1973) 297.[89] BLANN, M., Chicago Operations Office, US Department of Energy, Chicago, IL,
Rep. COO-3494-29( 1976).[90] WAPSTRA, A.H., BOS, K., At. Data Nucl. Data Tables 19 3 (1977).[91] MYERS, W.D., SWIATECKI, W.J., Ark. Fys. 36 (1967) 343.[92] BLANN, M., DOERING, R.R., GALONSKY, A., PATTERSON, D.M., SERR, F.E.,
Nucl. Phys. A2S7 (1976) 15.[93] McGEE, T., RAO, C.L., SAHA, G.B., YAFFE, L., Nucl. Phys. A1S0 (1970) 11.[94] HILLE, M., HILLE, P., UHL, M., WEISZ, W., Nucl. Phys. A198 (1972) 625.[95] LITTLE, F.E., LAGUNAS-SOLAR, M., Int. J. Appl. Radiat. Isot. 34 (1983) 631.[96] LUNDQVIST, H., MALMBORG, P., LANGSTROM, B., CHIENGMAI, S.N., Int. J.
Appl. Radiat. Isot. 30 (1979) 39.[97] DeJONG, D., BRINKMAN, G.W., LINDNER, L., Int. J. Appl. Radiat. Isot. 30 (1979) 188.[98] NOZAKI, T., IWAMOTO, M., ITOH, Y., Int. J. Appl. Radiat. Isot. 30 (1979) 79.[99] WEINREICH, R., KNIEPER, J., Int. J. Appl. Radiat. Isot. 34 (1983) 1335.
[100] DIKSIC, M., GALINIER, J.-L., MARSHALL, H., YAFFE, L., Phys. Rev. C 19 (1979)1753.
[101] HOFFER, P.B., et al., J. Nucl. Med. 14 (1973) 172.[102] GRABMAYR, P., NOWOTNY, R.( Int. J. Appl. Radiat. Isot. 29 (1978) 261.[103] COLLE, R., KISHORE, R., Phys. Rev. C 9 (1974) 2166.[104] WILKINS, S.R., et al., Int. J. Appl. Radiat. Isot. 26 (1975) 279.[105] PAANS, A.M.J., VAALBURG, W., VAN HARK, G., WOLDRING, M.G., Int. J. Appl.
Radktvlsot. 27(1976)465.[106] DIKSIC, M., YAFFE, L.( J. Inorg. Nucl. Chem. 39 (1977) 1299.[107] SYME, D.B., et al., Int. J. Appl. Radiat. Isot. 29 (1978) 29.[108] LEBOWITZ, E., et al., J. Nucl. Med. 16 (1975) 151.[109] LAGUNAS-SOLAR, M.C., JUNGERMAN, J.A., PEEK, N.F., THEUS, R.M., Int. J.
Appl. Radiat. Isot. 29(1978) 159.[110] QAIM, S.M., WEINREICH, R., OLLIG, H., Int. J. Appl. Radiat. Isot. 30 (1979) 85.[ I l l ] QAIM, S.M., STOCKLIN, G., WEINREICH, R., Int. J. Appl. Radiat. Isot. 28 (1977) 947.[112] WEINREICH, R., SCHULT, O., STOCKLIN, G., Int. J. Appl. Radiat. Isot. 25 (1974) 535.[113] MICHEL, R., GALAS, M., Int. J. Appl. Radiat. Isot. 34 (1983) 1325.[114] DIMBYLOW, P.J., National Radiological Protection Board, Harwell, UK, Rep. NRPB-R78
(1978).
3-2. ACTIVATION CROSS-SECTIONSFOR ELEMENTS FROM LITHIUM TO SULPHUR
P. ALBERT, G. BLONDIAUX, J.L. DEBRUN,A. GIOVAGNOLI, M. VALLADONCentre d'etudes et de recherches par irradiations,Centre national de la recherche scientifique,Orleans, France
Abstract
ACTIVATION CROSS-SECTIONS FOR ELEMENTS FROM LITHIUM TO SULPHUR.The paper presents cross-sections for nuclear reactions yielding radioisotopes. Since the
presentation is restricted to light elements (up to sulphur included), cross-sections for reactionswith heavy ions are of interest and have been included.
1. INTRODUCTION
This chapter presents the cross-sections for those nuclear reactions thatyield radioisotopes. Since this compilation is restricted to light elements (up tosulphur included), the cross-sections for reactions with heavy ions are of interestand have been included. For various reasons, a number of reactions are missing.More data, on these and on the reactions presented, can be found in Refs [1,2].
LITHIUM
Protons
7Li(p,n)7Be
figure 1
Curves in Figure 1 (d)
6Li(1Van)150
6LiC1*N,pn>18F
7Li(14N,a2n)150
7Li<Vp2n)18F
479
00O
BERYLLIUM
Helium 3
9Be (3He,n)11C
Figure 2
Helium A
9Be(a,2n)11C
Figure 2
U N
9Be(1V«n)18F
Figure S
9 Be( 1 4 N, 1 3 N) 1 0 Be
Figure 6
16o
9 Be( 1 6 O,p) 2 AN a
Figure 3
9Be( 1 60,2n)Z 3Mg
Figure 3
18o
9Be(1 80,2a>1 90
Figure A
9Be(1 8O,p2n)2 4Na
Figure A
9Be(1 8O,pn)2 5Na
Figure A
1 9F
9Be<19F,2a)2°F
Figure 3
9Be(19F,pa)23Ne
Figure 3
9Be(19F,2n)26M
Figure 3
a
Hn
e.
BORON
Protons
1Vp,n>11CFigure 7
Deuterons
1W>1 1cFigure 7
11B(d,2n)11C
Figure 7
Helium 3
11B(3He,p2n)11C
Figure 8
10B(3He,Pn)11C
Figure 8
11B(3He,n)13N
Figure 8
Al l curvesFigure 9
1W5O>9Be
10B(HN;8F)6Li
1OB(1V1C)13C
10B(1V13N)11B
11B(UN,p)24Na
160
Al l curvesFigure 3
10B(16O,2a>18F
10B(16O,na)21Mj
1OBC16O,2p)24Na
18oAl l curves
Figure 4
11B(1iWV
1lB(18O,pa)2V
11B(18O,na)^Na
11B(180,a)25Na
11B(18O,np)27Mg
1 1B(1 80,3O)2 6Al
lOB(18O,2a)2OF
19F
Al l curvesFigure 10
1W8F)11B
1 0 B( 1 9 F, 1 8 O) 1 1 C
10BC19F,ap>24Na
CARBON
Protons
12C(p,pn)11C
Figure 11
Oeuterons
12CCd,n)13N
Figure 12
Helium 3
12C(3He,n>U0
Figure 13
12C(3He,a)11C
Figures 13and 14
12CC3HeV3N
Figure 15
Helium
12C(a,n)
Figure
4
1 5 o
I6.
12C(UN,a)22Na
Figure 17
12C(1y2p)24Na
Figure 17
Figures 5and 17
12C(1V13N)13C
Figure 18
16o
12C(1Vn)2?Si
Figure 3
12
12
18o
C(1Vp)29Al
Figure 19
C(1 80,pn)2 8Al
Figure 19
A l l curvesFigure 10
1 2C(1 9F,
12CC19F
13C(19F
2p)29Al
18F)13C
,2a)24Na
>
wm
s
PART 3-2 483
NITROGEN
Protons
H N ( P / a ) 1 1 C
Figure 20
1 4N(p,2a) 7Be
Figure 20
14N(p,n>140
Figure 21
Helium 3
1V3He,pn)150Figure 23
14NC3He,a)13N
Figure 23
Helium 4
1W)1?FFigure 22
OXYGEN
Protons
160<p,a>13N
Figure 24
Deuterons
160(d,n)17F -
Figure 25
1 6 ' 1 7 ' 1W> 1 8F
Figure 25
Tritons
160Ct,n)18F
Figure 26
Helium 3Al l curvesFigure 27
16OC3He,X)18F
160C3He,O)1S0
1 60(3He /2a)1 1C
160(3He,an)140
160(3He,pn)17F
Helium 4
160Ca,X>18F
Figure 28
1 4N
1 60(1 4N,2p)2 8Al
Figure 29
160C1V8F)12C
Figure 29
FLUORINE 004
Deuterons
1 9 F(d,dn) 1 8 F
Figure 25
Tr i tons
19F(t,d>2°F
Figure 30
1 9F( t / P ) 2 1F
Figure 30
Helium 3
19FC3He,«>18F
Figure 31
19F(3He,2p)20F
Figure 31
Helium 4
19F(o,n)22Na
Figure 31
U N
1 9F(1V5N)1 8F
Figure 32
19,.,14., , ,30nF( N,p2n) P
Figure 32
1 9F
19F C19F ;8F )20 f
Figure 33
NEON
>
Oeuterons
2V(d,a)18F
Figure 29
Helium 3
20Ne(3He/X>18F
Figure 29
SODIUM
Deuterons
2 3 Na(d,p) 2 4 Na
Figure 34
Tritons
23Na(t,p)25Na
Figure 30
Helium 3
23Na(3He,2p)24Na
Figure 35
2 3Na(1y1 3N)2 4Na
Figure 6
1 8oA l l curves
Figure 4
23Na<18O,3n)38K
2 3Na(1 8O,1 70)2V
2 3NaC 1 8O, 1 6O) 2 5t e
19F
2 3 Na( 1 9 F, 1 8 F) 2 4 Na
Figure 33 "0
70
MAGNESIUM
&
Protons
Mg(p ,xn ) 2 6 Al
Figure 36
Mg(p,axn> Na
Figure 36
Deuterons
26U . . x 27.,Mg(d,p) Mg
Figure 34
Tritons
26Mg(t,p)28Mg
Figure 37
Mg(t,axn)24Na
Figure 37
Mg(t,x)27Mg
Figure 38
26Mg(t,n)28Al
Figure 38
2Sg(t ,n) 2 6 mAl
Figure 38
Helium 3
26M9(3He,p)28Al
Figure 39
2<W3He,2p)27Mg
Figure 39
Mg(3He,X)24Na
Figure 39
Helium 4
26Mg(a,2p)28Mg
Figures 37and 40
24Mg<ivaPxn> Na
Figure 37
26Mg(a,p)29Al
Figure 40
U NCurves inFigure 6
2V1V13N>25Mg
2 5Mg(1 4N,1 3N)2%
2 6Mg(1V1 3N)2 7Mg
ALUMINIUM
Protons
Curves i nFigure 36
2 7 Al (p ,pn) 2 6 Al
Al(p,apn) Na
Tr i tons
2 7Al( t ,apn) 2 4Na
Figure 37
2 7 A l ( t , 2 p ) 2 %
Figure 37
2 7 Al ( t ,d ) 2 8 Al
Figure 42
2 7Al(t,p)2 9AL
Figure 42
Helium 3
Curves inFigure 43
27Al(3He,2a)22Na
27AU3He,a2p)24Na
27AU3He,3p)27Mg
27AU3He,2p)28Al
Helium 4
27Al(a,4p5n)22Na
Figure 41
27Al(a,X)24NaFigures 37
and 41
27Al(a,3p)28MgFigures 37
and M
27. , , ,30DAl<a,n) P
Figure 44
1 2 c
Curves inFigure 45
2 7AU1 2C,X)1 8F
2 7Al(1 2C,X)2 4Na
2 7 AU 1 2C / X) 3 2 P
2 7 Al( 1 2 C / X) 3 4 m Cl
U N
27AK1VX)18F
Figure 45
27Al(1Vx>2ANa
Figure 45
27AU1Vp2n)3S
Figure 32
1 60
Curves inFigure 45
27AU16O,X)24Na
2 7 A U 1 60 / X ) 1 8 F
K
7)
OOJ
488 ALBERT et al.
SILICON
Protons
30Si(p,3p)28Mg
Figure 48
SiCp,4pxn) Na
Figure 48
SiCp,X)26Al
Figure 36
Si(p,X) Na
Figure 36
Tritons
A l l curves inFigure 47
3 0SiCt,a>2 9Al
29 28.,S i ( t , a ) A l
28Si<t,n>3°P
Helium 3
28Si(3He,p)30P.
Figure 46
Helium 4
28Si(a,d)30P
Figure 46
PHOSPHORUS
Protons
3 1 . , ,30DP(p,pn) P
Figure 44
31O , . ,28UP(p,4p) Mg
Figure 48
31P(p,5p3n)24Na
Figure 48
Helium 4
31P(a,n)34raCl
Figure 49
U N
31p(1Vpn)43Sc
Figure 50
3 1 P ( 1 V P > 4 4 S C
Figure 50
PC N,p) Sc
Figure 50
31PC1VP)"SC
Figure 50
3 1PC 1V 1 3N) 3 2P
Figure 51
PART 3-2 489
SULPHUR
Protons
34,., ,34m,,
Figure 49
S<p,5pxn) Mg
Figure 48
24S(p,6pxn) Na
Figure 48
Oeuterons
3 2 SCd,a ) 3 0 P
Figure 46
3 2 SC 1 4 N,P> W T i
F igure 52
3 2 S ( 1 4 N , 2 p ) A 4 S c
Figures 50 and 52
3 2 S ( U N , 2 p ) 4 4 m S c
Figures 50 and 52
3 2 S ( 1 4 N , 2 P n ) 4 3 S c
Figures 50 and 52
32S<1V2a)38\
Figure 52
3 2 SC 1 V 3 N> 3 3 S
Figure 52
(b)
(a)600
500
f 400 -c
I 300
2 200
100 -
LiF target a, Pt backingLiF target b, Al backingThick LiF targets, Al backing,weighed for determination ofthe absolute cross-section (±5%
,1.8814 - assumed threshold
1.8 1.9 2.0 2.1 2.2 2.3 2.4
Laboratory proton energy (MeV)
2.5
10
- o C
• N
- X 0 (CuO target)
4 0 (SiO2 target)
I 10
0.1
>
w
I I I I
103
20
He energy (MeV)
30
(c )
0.0120
JHe energy (MeV)
(d )200
100
50
20
10
5
3 2
0.5
0.2
0.1
0.05
0.02
0.01
Threshold energies (or the reactions7Li('Vdn»18F ^i(1Vp2n, l8F 18p
, , !_
/ V - ^ 18F "from ^ S/ Alkhazov et al. S\-
/ °/ 15O
• -7 * 15O ofrom/ Alkhazov et al.
14N + 7Li
10 15 20 25 30 35 40 5 10 151 4 N lab. energy (MeV)
20 25 30 35 40
"V
FIG. I. Production of nBe by proton irradiation of (a) nLi [3] and (b, c) 3He irradiation of C, N, O, F, Mg, Al and Si [4], (d) Production of 1SO andisF by irradiation of 6Li and nLi with UN [5]. (References within figures can be found in the original source.)
492 ALBERT et al.
EM12C) (MeV)
30 35 45 50 55 60
0 4 8 12 16 20 24 28 32 36 40 44
E'ab (MeV)3He
E* (13C) (MeV)
20 22 24 26 28
E l a b (MeV)
32
FIG. 2. Production of 11C by irradiation of Be with *He and 3He (upper horizontal scalesrepresent the excitation energies of the compound nuclei) [6].
PART 3-2 493
Oo
20 25 30 15
15 25 30 15 20 25
Incident energy (MeV)
FIG. 3. Reactions of 160 on 9Be, 10B and 12C, and of l9F on Be [7].
30
100
10
- / ^
/
/ . / ^ ^
/ / 9Be+19F
1 1 1
20 p
2 3Ne
" 26AI
i
30
494 ALBERT et al.
100 -
22 24 26 28 20 25 30
Incident energy (MeV)
FIG. 4. Reactions of nO on 9Be, 10B, nB and 23Na [7].
PART 3-2 495
500 -
10 20 30 40 50I4N ENERGY [MeV]
60 70
FIG. 5. Production of 1SF by irradiation of Be with I4/V [8].
496 ALBERT et al.
0.01
16 18 20 22 24 26 28
Laboratory energy (MeV)
0.01
16 18 20 22 24 26 28
Laboratory energy (MeV)
FIG. 6. (MN, 13N) reactions on 9Be, nC, 160, 23Na, ™Mg, 2sMgand 26Mg [9].
PART 3-2 497
6 8 10 12 14 16 18 20 22 24 26 28EJf (MeV)
E*('2C) (MeV)25 30 35
10B(d.n)11C
6 8-lab
10 12 14 16
24
(MeVI
E* (13C) (MeV)28 30
FIG. 7. Reactions producing UC by irradiation of boron with protons and deuterons (upperhorizontal scale is the excitation energy of the compound nucleus) [6].
498 ALBERT et al.
10-
10
10
10B(3He,pn)11C
B+3He -
1lB(3He.n)
0 5 10 15 20 25 30 35
Beam energy (MeV)
FIG. 8. Activation of B by irradiation with 3He. (Curves from three different sources aregiven for 10B (3ffe, pn) nC. References for the curves are in Ref. [10]J
io26H
M 97£ 10 -
10,-29
l 0 B( 1 4 N. 1 5 O) 9 Be 1 0B( 1 4N. 1 8F) 6L
1 0 B( 1 4 N. 1 1 C) 1 3 C
1 OBI 1 4N 11 3NI 1 1B
10 12 14 16 18 20 22 24 26
Lab. energy (MeV)
FIG. 9. Reactions induced on 10B and nB by 147V [ 11 ].
PART 3-2 499
10.4
19FON10B
Present data
Data from Ref.7
10 12 14 16 18 20 22 24 26 28
Lab. energy (MeV)
10"
io1H
io°H
io-1H
10.3
19F ON CARBON
1 2 C( t 9 F , 1 8 F) 1 3 C
16 18 20 22 24 26 28 30
Lab. energy (MeV)
FIG. 10. Reaction of19Fon 10B, nC and 13C [12]. (Reference within the figure can befound in the original source.)
500 ALBERT et al.
100 -
10 20 30 40 50
Proton energy (MeV)
60 70
FIG. 11. The nC (p, pnj nC reaction [13].
225
200
175
150
3E 125D100
75
50
25
0
1
-
"" y
- JV---1
I 1 • i
1 2 C ( d . n ) 1 3 N
•A .j
1 1 1 1
1 >
-
/ -
-
-
-
-
1 1
1.0 1.5 2.0 2.5 3.0 3.5
Deuteron energy (MeV)
4.0
FIG. 12. ThenC Id, n) 13N reaction [ 14].
4.5 5.0
PART 3-2 501
20
15
10
o5 5
12C(3He.n)14O
•t I
•»l
THRESHOLDM
.'2
200
100
12C(3He.a)11C
3 4
Energy (MeV)
. . •
FIG. 13. Excitation functions for the 12C(3He,a)nC and nC(3He,n)l*0 reactions. The errorin the absolute cross-section is estimated to be ±15% [15].
502 ALBERT et al.
10 15 20 25Beam energy (MeV)
30 35
FIG. 14. Various curves for the 12C(3He, a) nC reaction [10].
5 10 15 20 25 30 35
Beam energy (MeV)
FIG. 15. Different experimental curves for the 12C(3He, d) 1ZN reaction [10].
PART 3-2 503
16 17 18
Excitation energy (MeV)
19 20 21 22 23 24
25
20
(a.n,,) THRESHOLD
12C(a.n)15O
11 12 13 14 15 16 17 18 19 20 21 22 23
FIG. 16. The excitation function of the total neutron cross-section for the 12C (a, n) 1SOreaction [16].
504 ALBERT et al.
10-24
io-25H
S i o 2 7 -6
10,-29
1 2C(1 4N.a)2 2Na
1 2C(1 4N.2P )2 4Na
1 2C(1 4N.2a)1 8F
0 5 10 15 20 25 30 35
Energy (MeV)
FIG. 1 7. Reaction of nC with 14/V ions [17].
10
10 -
i
10"' -
10
I I ' I I I
_/>2C|14N.13N) l3C
1 1 1 1 I I
1 J 1 1 I 1 1 1 1 1 1 1 \y
1 6 O | 1 4 N . 1 3 N ] ' 7 O /
1 6 O( 1 4 N. 1 5 N) 1 5 O^/
-16O(14N.15N)15O , ' ' /•
••
. . _ 1 6 O ( 1 4 N 1 3 N ) 1 7 O
/ Ref.191f
_ //
/
/ Present data"" C.B. Hose, E. Newman ""
, unpublished data ORNL,.2
26 30 34 38 14 18 22 26 30 34 38 42
Laboratory energy (MeV)
FIG. 18. Reaction of l*Nwith I2C and l6O. Details on the ORNL data can be found in
Ref. [S).
PART 3-2 505
100
0.01-
10 15 20 25 30Oxygen lab. energy (MeV)
35
FIG. 19. Production of 2*Al and 29Al by irradiation of 12C with 18O, and of1AC by 16O[18].
506 ALBERT etal.
( a )
2<>0
— 200Z
o
ino:o
8 0 -
4 0 -
l 4 N(p .d ) "C
. Present data- - Epherre and Seide
4 Laumeretal.o MacLeod and Reid. Blaser et al.
: fv t t: ti 11 t 11
a io 12 14 16 it>
PROTON ENERGY (MeV)
20
( b )60
5 0
4 0
O
O 30UJv>tomOcro_i 20
o
IO
I ' I ' I • I • I
'N(p,2ot) 7Be
• Present data
Epherre and Seide
a Laumer et al.
. 1 , 1 , I i I . I . I i I i I16 18 20 22 24PROTON ENERGY (MeV)
26
FIG. 20. Production of (a) nC and (b) 1Be by irradiation of l*N with protons [ 19].(References within figures can be found in original source.)
PART 3-2 507
100
50
i\ 10
E | ab (MeV)
"7i ' ' ' 20~14... ,17_N(ct,n) F
%J^,
300
1016O(d.n)17F
15
10 15 Ee x p(MeV) 20
G. 2i. Production ofllF by irradiation of 147V with *He, and of 16O with deuteronsf°HF = calculation from Hauser-Feshbach theory) [20].
10
S 5
H
14N(p.n)14O
I ' I I I I I I I
100
50
6 7 8 9 10 11 12 13 14 15Energy (MeV)
FIG. 22. The 14JV(p, n)l*O reaction. Curve A: Ref. [21]; curve B: Ref [22].
508 ALBERT et al.
10"
10'
o
10
10
14N(3He.pn)15O 15Q
1 4N(3He.a)1 3N
. I . . . .
5 10 15 20 25 30 35Beam energy (MeV)
FIG. 23. Production of 1$0 and 13N (curves 1 and 2) by irradiation of 14N with 3He [10].
100
.o
£ 50
oO
10 11 12 13 14 15(E p ) | a b (MeV)
FIG. 24. The^O (p, a) 137V reaction [23 ].
PART 3-2 509
(a )
100
8 10
10 20Ed (MeV)
• Experimental pointsA Corrected points
( b )
10 20Ed (MeV)
30
FIG. 25. Production of 1SF by irradiation of fa) oxygen and (b) fluorine with deuterons [24].
510 ALBERT et al.
400-
300-
200-
100-
16O(«.n)18F
E (MeV)
FIG. 26. Production of18Fby bombardment of oxygen with tritons [25].
PART 3-2 511
10-
10"
16O(3He.X)18F
1 6O(3He.a)1 5O
'6O(3He.pn)17F
l 6O(3He.an)1 4O
10 15 20 25Beam energy (MeV)
30 35
FIG. 27. Production of various radioisotopes by bombardment of oxygen with 3He [10].
512 ALBERT et al.
400
0 5 10 15 20 25 30 35 40
FIG. 28. Production ofl%Fby the 16O(3He, XJ1&Fand i6O(a, Xj^F reactions [26]
PART 3-2 513
(a )
300
0 5 10 15 20 25 30
Energy (MeV)
Energy (MeV) for d
5 10 15
(b )
0 10 20 30 40
Energy (MeV) for 3He
FIG. 29. (a) Production of 2*Al and I 8F by irradiation of l60 with 147V [11 ]; (bj productionof 18F by irradiation of Ne with 3He and deuterons [26].
100
50
n
Na(t.p) °Na
* •
I • •*1 • *
1
80 -
60 -
, 0
20
0
1 9F(t .p)2 1F
40
I
' 20
I
1 9F(t .d)2 0F
• • •1.5 2.0 2.5
t3.0 1.5
,i-
2.0 2.5
Triton energy (MeV)
3.0
FIG. 30. Reactions with F and Na induced by low energy tritons [27].
PART 3-2 515
1
7 /[19F(3He
i I
4V ;18f "
,a)18F j
O 10 20 30E3 (MeV)
500
400
_e 300b
200
100 -
19F(u,n)22Na
3 4 5 6 7 8 9 I 0
Ea (MeV)
FIG. 31. Reactions induced by lHe [28] and *He [29] on 19F.
516 ALBERT et al.
10.2.
10-2-
10.-3.
1 9 F( 1 4 N. 1 5 N) 1 8 F
( a )
10 12 14 16 18 20 22 24 26 28
1 4 N lab. energy (MeV)
50
3 0 P f r o m 1 4 N o n 1 9 F
1 4 N o n 2 7 A I
( b )
14 16 18 20 22 24 26 28
E|ab ( M e V >
FIG. 32. Reactions induced by 14/V on (a) 19F [30J and on (bj 19F and 2-7Al [31 ].
PART 3-2 517
101
5-
o23Na(19F.18F)24Na
Curves represent present data
26 28 30 32 34 36 38 40 4224SF lab. energy (MeV)
FIG. 33. (l9F, 1SF) reactions on 23Na and 19F [30].
3X10 3r
10 15 20 25
projected ~ Ethreshold <M e V '
30 35 40
FIG. 34. (d, p) reactions on 23Na (curves la-Id, different authors) and on 16Mg (curve 2) [2].
518 ALBERT et al.
10 15 20 25 30 35Beam energy (MeV)
FIG. 35. The "Na^He, 2pJwNa reaction (data from Ref. [32]; figure from Ref. [10]/
PART 3-2 519
0 10 20 30 40 50 60Proton energy (MeV)
0 10 20 30 40 50 60Proton energy (MeV)
FIG. 36. Production of the long lived radioisotopes (a) 26Al and (bj 22Na by proton irradiationof Mg, Aland Si [33].
520 ALBERT et al.
100
-o 10
0.1
: f
2%
Mg +t
A, . , / J>
jl
(a) :
Mg + a
Al + o/
10 20 30 40Energy (MeV)
10 20 30 40Energy (MeV)
FIG. 3 7. Production of (a) 28Mg and (b) 2ANa by irradiation of natural Mg and AI by tritonsor a-particles [34].
PART 3-2 521
80
S 40
" 2 4M9(t .n)2 6 mAI• •T* . *
(a )
3 E.
300
- 200
100
26Mg(t.n)28Al -y
A-
( b )
1 227,
3 E.
10
Mg+t- Mg - V
(c )
FIG. 38. Production of (a) 26mAl, (b) 2iAl and (cj 27Mg by irradiation ofMg with low energytritons [27].
522 ALBERT etal.
10-
10,2 .
10' -
10°
26Mg(3He.p)28AI28A|
' *[ /
26Mg(3H,
- 27Mg
.27i.2p) Mg
Mg+3He . 2 4 N a
10 15 20 25 30 35Beam energy (MeV)
FIG. 39. Production of2iAl, 27Mg and wNa by irradiation of Mg with %He [10].
I 10°:
10"
10,-2.
26Mg(a,p|29AI
Q-value (a,2p)
26Mg(a.2p)28Mg
0 20 40 60 80 100 120 140 160 180Incident a-particle energy (MeV)
FIG. 40. Reactions with 16Mg induced by high energy a-particles [35].
PART 3-2 523
1.0-
iS 0.1-
001-Q- value
"AI |a.3p)? 8Mg
20 40 60 80 100 120 UO 160
Incident a-particle energy (MeV)
n
oo
'Al la.ipSnTNo
viola-. "Al(a.'B.I»No
20 40 60 80 100 120 U0 160 180
Incident a-particle energy (MeV)
FIG. 41. Reactions with 21Al induced by high energy a-particles [35].
524 ALBERT et al.
100
80
1 60
40
20
27AI(t.d)28AI
Triton energy (MeV)
100
140
120
100
80
60
40
20
0
27AI(t.p)29AI
-i
--
*•1 p2 3
Triton energy (MeV)
FIG. 42. Activation of Al by low energy tritons [27].
10-
G 10'
10
He,2p) Al
27,Mg
2 7AL(3He /3p)2 7Mg
no
50
0 5 10 15 20 25 30 35 0 5 10 15 20 25 30 35 0 5 10 15 20 25 30 35
Beam energy (MeV( Beam energy (MeV) Beam energy (MeV)
FIG. 43. A ctivation of Al with *He (and after various authors for Na and ™Na) [ 10],
526 ALBERT et al.
1 0 3
1 0 2
10 1
r
r /
27AI(o ,n)30P 1
\ ]
10 3020 30 20
Energy of the incident particles (MeV)
FIG. 44. Production of 30P through various nuclear reactions [36].
100
20 40 60 80 100 12012,C beam energy (MeV)
20 40 60 80 100 120 140 160
0 beam energy (MeV)
100 100 r
20 40 60 80 100 12012-
20 40 60 80 100 120 14014,,
C beam energy (MeV) N beam energy (MeV)
FIG. 45. Some activation products obtained by irradiation of 21Al with 12C, 147V and 16O [37].
PART 3-2 527
E 101
7 30 40
1 0 '
32S(d,a)30P
• . / • I
28Si(a.d)30P
1 1 1 1
10 20 10 20Incident particle energy (MeV)
30
FIG. 46. Formation of30P through different nuclear reactions [38].
528 ALBERT et al.
40
20
30Si(t.4He)29AI
2 3Triton energy (MeV)
60
f 40
20
0
29Si<,.W8A.
•
•
t
•
/
1
80
60
1o 40
20
28Si(t.n)30P
r
2 3
Triton energy (MeV)2 3
Triton energy (MeV)
FIG. 47. Activation of Si with low energy tritons [27].
0.1
8 0.01
0.001
c 31P(p,4p)28Mgt CI(p,6pxn)28Mgo S(p,5pxn)28Mg, K(p,8pxn)28Mg
50 100 150 200
Incident proton energy (MeV)
1.0
gS 0.1
0.01
o,. Ar(p,7pxn)28Mga Si(p,3p)28Mg
10
50 100 150Incident proton energy (MeV)
XIE
8
0.01
0 31P(p,5p3n)24Na. Si(p,4pxnl24Na* S(p,6pxn)24Na. CI(p,7pxn)24Nao K(p,9pxn)24Na• Ar(p,8pxn)24Na
100 150 200Incident proton energy (MeV)
7)
FIG. 48. Production of2iMgand MNa by irradiation of Si, Pand S (also Cl, K, Ar) with high energy protons [39].
530 ALBERT et al.
Excitation energy in Cl (MeV)
126 12.8 13.0 13.2 13.4 13.6 13.8 14.0
_
I
•sec
tio
nal
cro
sslo
t,
15
12
9
6
3
0
t t i
80 keV Ca3P2 target
-
-
' 6.360 < 0.010 A
( a )
AAJif
Ik/JY -
7J .
-6.4 6.6 6.8 7.0 7.2 7.4 7.6 7.8
Alpha energy (MeV)
Excitation energy in Cl (MeV)12.6 12.8 13.0 13.2 13.4 13.6 13.8 14.0
100 -
6.4 6.6 6.8 7.0 7.2 7.4 7.6 7.8 8.0
Proton energy (MeV)
FIG. 49. Production of 34mCl by irradiation (a) of P by a-particles (reaction 31P(a, n)34mCl)and (b) of S by protons (reaction **S(p, n)MmCl)(inset: ground state threshold) [40].
PART 3-2 531
100-
50-
20-
ID-
S'
3 2-
o 1"
0.5-
0.2-
0.1-
0.05-
0.02-
0.01-
f 1 4 4«^-1 I I 14N +
32S
/ / /11
18 22 26 30 34 38 4214N E|ab (MeV)
FIG- 50. Some activation reactions induced by bombardment of 31Pand 32S with 14/V [41 ].
532 ALBERT et al.
0.02-
0.01
' 1 9 F ( 1 4 N . 1 5 N ) 1 8 F ^ 3 1P( 1V 1 3N) 3 2P
12 16 20 24 2818 22 26 30 34 38 421 4 N lab. energy (MeV)
FIG. 51. Activation of l9F(lsF) and 3lF(l3N, 32P) by irradiation with 147V [5].
PART 3-2 533
2214,
24 26 28
N lab. nitrogen energy (MeV)
( a )
30
5X10
10,-29
( b )
18 20 22 24 26 28 3014,N lab. energy (MeV)
FIG. 52. Some activation products obtained by irradiation of 32S with 14JV. (a) 32S + 14Af ->• 38£,"Sc, "Sc, "mSc and «5Ti; (b) 32S + ' V -* i3N [42].
534 ALBERT et al.
REFERENCES
[ 1] MUNZEL, H., et al., Karlsruhe Charged Particle Reaction Data Compilation, PhysicsData, No. 15, Fachinformationszentrum, Karlsruhe (1982).
[2] KELLER, K.A., LANGE, J-, MUNZEL, H., PFENNING, G., "Q-values and excitationfunctions of nuclear reactions", Excitation Functions for Charged Particle Induced NuclearReactions (Landolt-Bornstein New Series Group I), Vol. 5b, Springer-Verlag, Berlin (West)(1973).
[3] MACKLIN, R.L., GIBBONS, J.H., Phys. Rev. 109 (1958) 105.[4] MIKUMO, T., SEKI, R., TAGISHI, Y., FURUKAWA, M., YAMAGUCHI, H., Phys. Lett.
23(1966)586.[5] GAEDKE, R.M., TOTH, K.S., WILLIAMS, J.R., Phys. Rev. 140 (1965) B296.[6] ANDERS, B., HERGES, P., SCOBEL, W., Z. Phys. A 301 (1981)353.[7] FALK, W.R., HUBER, A., MATTER, U., BENJAMIN, R.W., MARMIER, P., Nucl. Phys.
A140 (1970) 548.[8] REYNOLDS, H.L., ZUCKER, A., Phys. Rev. 100(1955)226*[9] HALBERT, M.L., HANDLEY, T.H., PINAJIAN, J.J., WEBB, W.H., ZUCKER, A., Phys.
Rev. 106(1957)251.[10] LAMB, J.F., Lawrence Berkeley Lab., University of California, Berkeley, Rep.
UCRL-18981 (1969).[11] REYNOLDS, H.L., SCOTT, D.W., ZUCKER, A., Phys. Rev. 102(1956)237.[12] GAEDKE, R.M., TOTH, K.S., WILLIAMS, J.R., Phys. Rev. 167(1968)957.[13] CUMMING, J.B., Nucl. Phys. 49 (1963) 417.[14] JASZCZAK, R.J., MACKLIN, R.L., GIBBONS, J.H., Phys. Rev. 181 (1969) 1428.[15] CIRILOV, S.D., NEWTON, J.O., SCHAPIRA, J.P., Nucl. Phys. 77 (1966) 472.[16] BLACK, J.L., KUAN, H.M., GRUHLE, W., SUFFERT, M., LATSHAW, G.L., Nucl.
Phys. A11S (1968)683.[17] REYNOLDS, H.L., ZUCKER, A., Phys. Rev. 96 (1954) 1615.[18] EYAL, Y., DOSTROVSKY, I., Nucl. Phys. A179 (1972) 594.[19] JACOBS, W.W., BODANSKY, D., CHAMBERLIN, D., OBERG, D.L., Phys. Rev. C 9
(1974)2134.[20] GRUHLE, W., SCHMIDT, W., BURGMER, W., Nucl. Phys. A186 (1972) 257.[21] NOZAKI, T., IWAMOTO, M., Radiochim. Acta 29 (1981) 57.[22] KUAN, H.M., RISSER, J.R., Nucl. Phys. 51 (1964)518.[23] FURUKAWA, M., et al., J. Phys. Soc. Jpn. 15 (1960) 2167.[24] TRAN, M.D., CHENAUD, A., GIRON, H., TOUSSET, J., in Modern Trends in Activation
Analysis (Proc. Int. Conf. Gaithersburg, MD, 1969) (DeVOE, J.R., Ed.), Vol. 2, USNational Bureau of Standards Special Publication 312, US Government Printing Office,Washington, DC (1969) 811.
[25] REVEL, G-, DA CUNHA BELO, H., LINCK, I., KRANS, L., Rev. Phys. Appl. 12(1977)81.
[26] NOZAKI, T., IWAMOTO, M., IDO, T., Int. J. Appl. Radiat. Isot. 25 (1974) 393.[27] BORDERIE, B., BARRANDON, J.N., J. Radioanal. Chem. 55 (1980)329.[28] LEE, D.M., LAMB, J.F., MARKOWITZ, S.S., Anal. Chem. 43 (1971) 542.[29] NORMAN, E.B., CHUPP, T.E., LESKO, K.T., GRANT, P.J., WOODRUFF, G.L., Phys.
Rev. C 30 (1984) 1339.[30] GAEDKE, R.M., TOTH, K.S., WILLIAMS, J.R., Phys. Rev. C 4 (1971) 98.[31] NEWMAN, E., TOTH, K.S., Phys. Rev. 129 (1963) 802.[32] HAHN, R.L., RICCI, E., Nucl. Phys. A101 (1967) 353.
PART 3-2 535
[33] FURUK.AWA, M., SHIZURI, K., KOMURA, K., SAKAMOTO, K., TANAKA, S., Nucl.Phys. A174 (1971) 539.
[34] NOZAK.I, T., FURUKAWA, M., KUME, S., SEKI, R., Int. J. Appl. Radiat. Isot. 26(1975) 17.
[35] PROBST, H.J., QAIM, S.M., WEINREICH, R., Int. J. Appl. Radiat. Isot. 27 (1976) 431.[36] SAHAKUNDU, S.M., QAIM, S.M., STOCKLIN, G., Int. J. Appl. Radiat. Isot. 30 (1979) 3.[37] LADENBAUER-BELLIS, J.M., PREISS, J.L., ANDERSON, C.E., Phys. Rev. 125 (1962) 606.[38] QAIM, S.M., OLLIG, H., BLESSING, G., Int. J. Appl. Radiat. Isot. 33 (1982) 271.[39] LUNDQVIST, H., MALMBORG, P., Int. J. Appl. Radiat. Isot. 30 (1979) 33.[40] UMBARGER, C.J., KEMPER, K.W., NELSON, J.W., PLENDL. H.S., Phys. Rev. C 2
(1970) 1378.[41] WILLIAMS, J.R.,TOTH,K.S., Phys. Rev. 138(1965)382.[42] FISHER, D.E., ZUCKER, A., GROPP, A., Phys. Rev. 113 (1959) 542.
3-3. THICK TARGET YIELDSFOR THE PRODUCTION OF RADIOISOTOPES
P. ALBERT, G. BLONDIAUX, J.L. DEBRUN,A. GIOVAGNOLI, M. VALLADONCentre d'etudes et de recherches par irradiations,Centre national de la recherche scientifique,Orleans, France
Abstract
THICK TARGET YIELDS FOR THE PRODUCTION OF RADIOISOTOPES.The paper presents data on reactions with hydrogen (protons, deuterons and tritons) and
helium (helium 3 and 4). Only yield curves are considered, while individual yields at a givenenergy are excluded.
1. INTRODUCTION
The tables that are presented here are limited to reactions with hydrogen(protons = p, deuterons = d and tritons = t) and helium (helium 3 = 3He andhelium 4 = a). They are also not complete because only yield curves have beenconsidered, while individual yields at a given energy have been excluded (forfurther details, see Ref. [1 ]). Finally, where several publications were available,only one was retained in order to keep the length of this chapter at an acceptablelimit. As a result, some references have probably been missed.
The yields were collected from a number of different publications and arepresented in various units which should be clearly understandable. Sincecomplementary details of interest could not be included, owing to the lack ofspace, readers are referred to the original publications cited with each figure.
537
538 ALBERT et al.
LITHIUM
Protons
Figure 1
Li(p,n) Be
E th = 1.88
Deuterons
Figure 2
LiCd,xn)7Be
BERYLLIUM
Helium
Figure
9Be(3He,
Eth =
3
JL
n)
0
11C
Helium
Fig
9Be(a
E t h
u r e
,2n)
4
3.
11
= 18.8
C
80R0N
Protons
Figure 1
B(p,axn) Be
Figure 4
1 Wn) 1 1 CEth = 3 - ° 2
Deuterons
Figure 2
B(d,axn) Be
Figure 4
B(d,xn)11C
Tritons
Figure 5
10B(t / 2n)11C
Eth = 0
Helium 3
Figure 4
10B(3He,pn)11C
Eth=°
Figure 4
11B(3He,n)13N
Eth = 0
Helium 4
Figure 4
B(a,xn)13N
PART 3-3 539
CARBON
Figure 6 for a l l reactions
Protons
13C(p,n>13N
E t h = 3.23
12C(p,pn)11C
E t h = 202S
Deuterons
12C<d,n)13N
Eth = °-33
12C(d,dn)11C
E t h = 21.84
Helium 3
12ccW>11c
12C<3He,pn)13N
E th = 7 " 2 2
Helium 4
12C(a,an)11C
Eth = 2 4 - 9 6
NITROGEN
Protons
E th * 3 ' 1 2
1AN(p,pn)13N
E t h = 11.31
Deuterons
Figure 8
E th = 0
14N(d,dn)13N
E t h = 12.06
14N(d,an)11C
Et(, = 5.88
Helium 3
14NC3He,a>13N
E t h = °
14NC3He,apn)11C
E t h = 12.92
Helium 4
E t h = 13.57
1 4N(a,xn)1 8F
540 ALBERT et al.
OXYGEN16 18
figure 9 for all reactions except 0(t,n) F (Figure 10)
Protons
1W>1 8FEth = 2 - 5 9
160(p,a>13N
Eth = 5 " 5 4
Deuterons
160Cd,an)13N
Eth = 8 - 3 7
0(d,xn)18F
Tritons
Fiqure 10
1 60(t ,n)1 8F
Eth = °
Helium 3
1 60<3He,p)1 8F
E t h = 0
160(3He,2a)11C
Eth = 6"3
Helium 4
160(a,pn)18F
E,.. = 23.2
160(a,2n)18Ne*18F
Eth = 29.73
FLUORINE19 22
Fiqure 11 for a l l reactions except F(a,n) Na (Figure 12)
Protons
19F(P ,Pn)18F
Eth = 1 0 - 9 9
Deuterons
19FCd,dn)18F
E th = 11.54
Helium 3
1 9F(3H e /a)1 8F
Eth = °
Helium 4
19F(a,ccn)18F
Eth = 12.63
Figure 12
19F(a,n)22Na
Eth = 2 - 3 6
PART 3-3 541
NEON
Deuterons
Fiqure 13
20NeCd,a>18F
E t h = °
MAGNESIUM
Tritons
Fiqure 14
26Mg(t,p)28Mg
Eth = °
Fiqure 16
24Mg(t,axn) Na
Helium 4
Fiqure 14
26Mg<a,2p)28Mg
E th = 1 1 " 9 1
Fiqure 15
25Mg(a,p)28Al
E t h = 1 ' 4
Fiqure 15
26Hg(a,p)29Al
E th = 3 - M
Fiqure 16
Mg(<»,apxn)24Na
542 ALBERT et al.
ALUMINIUM
Tritons
Fiqure 15
27Al(t,2p)28Mg
Eth = 2
Fiqure 16
27Al(t,apn)24Na
E th = 12.9
Helium 4
Figure 18
27AUa,n)30P
E th = 3 - 0 5
Figure 17
27Al(a,3p)28Mg
E t h = 24.82
Figure 17
27AUa,4p5n) Na
E t h = 90.8
Figure 17
27AUo,4p3n)24Na
E t h = 68.6
Figure 17
27Al(a,7Be)24Na
E th = 2 5 - 4
SILICON
Tritons
Figure 14
Si(t,3He,pxn)28
Figure 16
S i ( t ,a He,xn^4|ga
Helium 3
Figure 18
28Si<3He,p>30P
Eth = 0
Helium 4
Figure 18
28Si(a,d)30P
E t h = 13.72
PART 3-3 543
PHOSPHORUS
Protons
Figure 19
31P<p,4p)28Mg
E th = 3 2 " 3
Helium 4
Figure 20
31P«,,n)34mCl
E th = 6 " 3 9
SULPHUR
Protons
Figure 20
3AS(P/n)3AraCl
E th = 6 ' 4 7
Figure 19
S(p,5pxn) Mg
Deuterons
Figure 20
SCd,xn)3AmCl
Figure 18
32S(d,a)30P
E t h = °
Tritons
Figure 21
32S(t,n)3Al"ci
Eth = °
Helium 3
Figure 20
S(3He,pxn)34mCl
Helium 4
Figure 20
S(a,pxn) Cl
CHLORINE
Protons
Figure 19
Cl(p,6pxn)28Mg
Figure 20
3SClCP,Pn>34roCl
E th = 13.01
Oeuterons
Figure 20
37cL(d,P)38a
Eth = °
Figure 20
3 5Cl(d,dn)3 A mU
E t h = 13.37
Helium 3
Figure 20
37CU3He,2p)38Cl
E th = 1 " 7 4
Figure 20
35Cl(3He,a)34n!Cl
E t h = °
Helium 4
Figure 20
35CUa,an>34inU
E th = 1 4 ' 1 0
Figure 22
35CUa,n)38K
Eth = 6 - 5 4
544 ALBERT et al.
ARGON
Protons
Figure 19
28Ar(p,7pxn) Mg
POTASSIUM
Protons
Figure 19
K(p,8pxn)28Mg
CALCIUM
Protons
Figure 23
48CaCp,n)48Sc
Eth = °-67
Helium 4
Figure 24
40Ca<a,p)43Sc
Eth = 3" 9
Figure 24
48Ca(a,n)51Ti
Eth = °"33
PART 3-3 545
TITANIUM
Protons
Fiqure 25
Ti(p,xn)48V
Helium 3
Fiqure 26
Ti(3He,xn)48Cr
Figure 26
M< He,xn) Cr
Fiqure 26
Ti <3He,apxn>A'*mSc
Fiqure 26
Ti(3He/apxn)46rl+9Sc
Fiqure 26
Ti( He,apxn)47Sc
Fiqure 26
Ti(3He,apxn)48Sc
Fiqure 26
Ti<3He,pxn)48V
Helium 4
Fiqure 27
46Ti(a,n>49Cr
E t h = A.76
Fiqure 27
48Ti(a,n)51Cr
Eth = 2 - 9 3
Fiqure 27
4 9Ti(a,P )5 2V
E th = 2 ' 1 8
Fiqure 27
5 0 Ti (a ,p) 5 3 V
E th = 3 - 8 3
Fiqure 28
TiCc^xn^Cr
Fiqure 28
Ti(a,xnr1Cr
546 ALBERT et al.
VANADIUM
Protons
Figure 25
5Wn>51Cr
Eth = 1 - 5 7
Deuterons
Figure 28
51V(d,2n)51Cr
E th = 3.91
Figure 28
51V(d,4n)49Cr
E th = 2 7
Figure 28
51V(d,5n)48Cr
Eth = 3 7 " 8
Helium 4
Figure 29
51V(a,n)54Mn
E th = 2 - 4 6
CHROMIUM
Protons
Figure 25
52Cr(p,n)52Mn
E th = 5 " 6
Fiqure 25
52, , ,52muCr(p,n) Mn
Eth = 5 - 6
HeLiurn A
Figure 30
5CJ , ,53,.Cr(a,n) Fe
E th = 5 " 6
Figure 30
53Cr(a,p)56Mn
E th = 3 - 5
PART 3-3 547
MANGANESE
Helium 3
Fiqure 32
55Mn<3He,3n)55Co
Eth = 1 3" 7
Figure 32
55Mn(3He,2n)56Co
E t h = 3
Figure 32
55MnC3He,n)57Co
Eth = °
Helium 4
Fiqure 31
55Mn(ct,n)58Co
Eth = 3" 7 6
Figure 31
55Mn(a,2n)57Co
E t h = 12.96
Fiqure 31
Mn(a,an) Mn
E t h = 10.96
IRON
Protons
Fiaures 25, 33 and 34
Fe(p,xn)55Co
Fiaures 25 and 34
56C , ,56.Fe(p,n) Co
Eth = 5.44
Deuterons
Fiqure 34
Fe(d,xn)55Co
Figure 34
Fe(d,xn)56Co
Figure 34
FeCd,xn)57Co
Figure 34
Fe(d,xn)58Co
Helium 4
Figure 35
S4Fe(a,p)57Co
Eth = 1-9
Figure 35
54Fe(a,n)57Ni
Eth = 6- 2
548 ALBERT et al.
COBALT
Protons
Figure 36
59Co(p,p2n)57Co
Figure 36
59CoCp,3n)57Ni
Eth = 2 3 ' 4
Helium 3
Figure 37
59Co(3He,n)61Cu
E t h = °
Figure 37
59Co(3He,a)58Co
Eth = °
Figure 37
59Co<3He,ctn)57Co
E th = 0
Figure 37
59Co(3He,a2n)56Co
E t h = 10.3
Helium 4
Figure 38
59Co(a,2n)61Cu
Eth = 1 4 - 9
Figure 38
59Co(a,an)58Co
E t h = 11.15
Figure 38
59CoCa,a2n)57Co
E th = 2 0 - 3
Figure 39
Co(a,n) Cu
E = 5.4th
PART 3-3 549
NICKEL
Protons
Fiqure 40
NiCp,pxn)57Ni
Figure AO
Ni(p,axn)55Co
Figure 25
58Ni(p,a)55Co
E th = 1 - 3 7
Figure AO
Ni(p,axn) Co
Figure AO
Ni(p,pxn)56Ni
Figure 40
Ni(p,axn) Co
Figure AONi(p,axn)b8Co
Figure 25
Ni(p,xn)60Cu
Fiqure 25
Ni(p,xn)61Cu
Helium A
Fiqure A1
Ni(a,pxn) Cu
Figure A2
58Ni(a,p)61Cu
E th = 3 - 3
Figure A2
6°NiCa,n)63Zn
E th = 8 ' 4
Figure A3
6 0Ni(a /2n)6 2Zn
E t h = 18.2
Fiqure A1
Ni(a,pxn) Cu
Figure A1
Ni(a,pxn) Cu
550 ALBERT et al.
COPPER
Protons
Figures 23 and 25
6 3 Cu(p ,n ) 6 3 Zn
E t h = 4 - 2
Fiqures 23 and 25
6 5 Cu(p ,n ) 6 5 Zn
E t h = 2 - 1 6
Helium 4
Fiqures 44 and 46
6 3Cu<a,n)6 6Ga
E t h = 8
Fiqure 44
6 5Cu(a,n) 6 8Ga
E t h = 6 " 2
Fiqure 46
65Cu<a,2n)67Ga
E t h = 1 S
PART 3-3 551
ZINC
Protons
Fiqures 23, 25 and 46
Zn(p,xn) Ga
Figures 23. 25 and 46
Zn(p,xn)67Ga
Figures 23 and 25
Zn(p,xn) Ga
Deuterons
Figure 46
Zn(d,xn)66Ga
Fiqure 46
Zn(d,xn)67Ga
Helium 4
Figure 45
Zn(a,p) Ga
E th = 4.26
Figure 45
64, , .67,.Zn(a,n) Ge
£th = 9 - 8
Figure 45
66Zn(a,n)69Ge
E t h = 8
Figure 46
Zn(a,pxn) Ga
Figure 46
Zn(a,pxn) Ga
Fiqure 46
Zn(a,pxn) Ga
FiQure 46
Zn(a,xn)666e
Fiqure 46
Zn(a,xn) Ge
Figure 46
ZnCa,xn) Ge
GALLIUM
Protons
Figure 47
69GaCP,n)69Ge
E th = 3.06
552 ALBERT et al.
GERMANIUM
Protons
Fiqure 48
Ge(p,pxn) Ge
Fiqure 48
Ge(p,pxn) Ge
Fiqure 48
Ge(p,xn) As
Fiqure 48
GeCp/xn) As
Figure 48
Ge<p,xn)73As
Fiqure 48
74Ge(p,xn) As
Fiqure 48
Ge(p,axn) Ga
Fiqure 48
GeCp,axn) Ga
Helium 3
Fiqure 49
72Ge(3He,2n)73Se
E t h = 6.08
Fiqure 49
Ge(3He,xn)73Se
Helium 4
Fiqure 49
Ge(a,xn)73Se
Fiqure 49
72GeCa,3n)73Se
E th = 2 7 - 6
Figure 50
70Ge(a,n)73mSe
E t h = 8.36
Figure 50
72Ge(a,n)75Se
E th = 6 " 7
Fiqure 50
74Ge(a,n)77mSe
E th = 4 - 7 5
Fiqure 50
76Ge(a/n)79raSe
E th = 3 ' 1 6
PART 3-3 553
SELENIUM
Protons/Fiqure 51
7 6 Se( P / n) 7 6 Br
E th = 5 - 5
7 7SeCp,n)7 76r
E th = 2 - 2
8 2Se(p,n) 8 2Br
Eth = ° - 9
7 7SeCP /2n)7 6Br
Eth = 1 3
78SeCp,2n)77Br
E th = 1 2 " 8
Helium 3/Fiqure 52
Se(3He,xn)76Kr
Se( He,xn) Kr
Se(3He,xn)79Kr
Se(3He,pxn)75Br
Se<3He,pxn>76Br
Se(3He,pxn)?7Br
554 ALBERT et al.
BROMINE
Protons
Fiqure 53
Br(p,xn)77Kr
Deuterons
Fiqure 54
BKd,xn)?5Kr
Helium 3/Fiqure 55
Br( He,xr\) Rb
3 79Br( He,pxn) Kr
81Br(3He,2n)82mR
Eth = 2 " 8
Helium 4/Fiqure 55
79Br(a,2n)81Rb
Eth = 1 5 - 1
Br(o,xn)82mRb
b 81Br<a,2n)83Rb
E th = 1 2 - 9
BrCa,n) Rb
E t h = 4
Br(a,a2n) Br
E th = 2 0
KRYPTON
Al l curves in Fiqure 56
Protons
Kr(p,xn)79Rb
Kr(p,xn)81mRb
Kr(p,xn)81Rb
Kr(p,xn) Rb
Kr(p,xn)83Rb
KrCp,xn)84mRb
Kr(p,xn)8ARb
Kr(p,xn)86Rb
PART 3-3 555
RUBIDIUM
Protons/Fiqure 57
85_. , X84m_,Rb(p,pn) Rb
E t h = 10.65
85Rb(p,pn)84RbE,. = 10.65
Rb(p,p2n) Rb
E t h = 19.1
85Rb(p,p3n)82mRb
Eth = 3 0" 3
85Rb(p,p4n)81mRb
Eth = 3 9
85Rb(p,p4n)81Rb
Eth = 3 9
85Rb<p,3n)83Sr
Eth =
2 9- 6
85Rb<p,4n)82Sr
Eth = 3 8" 9
85Rb(p,5n)81Sr
Eth =
Rb(p,o3n) Kr
Eth = 2 7' 4
Helium 3/Fiqure 58
Rb(3Herxn)86mY
87Rb(3He/2n)88Y
E f h = 1.56
Rb(iHe,xn)87mY
87Rb(3He,5n)85mV
Eth = 3 3' 4
87Rb(3He,5n)85Y
Eth = 3 3- 4
Helium 4/Fiqure 58
RbCa,xn)86mY
OpRbCa,xn) Y
Rb(a,xn)87mY
85Rb(a,4n)85mY
Eth = 3 5- 9
85Rb(a,4n)85Y
Eth = 3 5" 9
556 ALBERT et al.
YTTRIUMFigure 59
Protons
89Y<p,n>89Zr
Eth = 3" 6 6
ZIRCONIUM
Figure 59
Protons
Zr(p,xn)95Nb
NIOBIUM
Figure 59
Protons
93Nb<p,n)93raMo
Eth
MOLYBDENUM
Protons
Figures 59 and 60
Mo(p,xn)94Tc
Fiqures 59 and 60
Mo(p,xn)95Tc
Figures 59 and 60
Mo(p,xn)96Tc
Figures 59 and 60
Mo(p,xn)"mTc
F_2 ure 60
93Mo(p,xn) Tc
Figure 60
100Mo(p,pn)99Mo
E th = 8 " 4
Helium 3/Figure 61
3 94Mo( He,xnr Ru
Mo(3He,xn)95Ru
Mo(3He,xn)97Ru
Helium 4
Fiqure 61
94Mo(a,xn) Ru
Fiqure 61
95Mo(a,xn) Ru
Fiqure 61
97Mo(a,xn) Ru
Fiqure 61
98«o(a,P)101Tc
Eth = 5 - 4
PART 3-3
RHODIUM
557
Protons
Figure 63
103Rh<p,axn)97Ru
Figure 64
103RhCp,p2n)101mRh
Eth = 1 6 ' 9
Figure 64
103RhCp,p2n)1°1Rh
E th = 16.9
Figure 64
103Rh(P,P3n)100Rh
E th = 26.9
Figure 64
103Rh(p,3n)101Pd
E th = 1 9 - 5
Figure 64
103RhCp,4n)100Pd
Eth = 2 8 - 3
Helium4/Fiqure 62
103RhCa,n>106mAg
E th = 7-"
103Rh(a,2n)1053Ag
E th = 1 6 ' 2
PALLADIUM
Protons
Figure
Pd(p,xn>
Figure
Pd(p,xn)
59
1tKAg
65
105.Ag
558 ALBERT et al.
SILVER
Protons/Fiqure 65
107A9<p,n)107Cd
E th = 2 " 2 4
Helium 3/Fiqure 66
AgC He,xn) In
109A9C3He,2n)110In
Eth = 3 " 6 5
1 0 9A3 (3He,n) l 1 1 In
E t h = °
CADMIUM
Protons/Fiqure 65
CdCp,xn)11OmIn
CdCp,xn)111mln
CdCp,xn)113mIn
Helium 3/Fiqure 67
Cd(3He,xn)113Sn
Cd(3He,xn)117mSn
Helium 8
Fiqure 67
CdCa,xn)113Sn
Fiqure 67
CdCa,xn)117mSn
Fiqure 68
1 1Wn)1 1 9 mSnEth = 4 - 3
Fiqure 68
116CdCa,3n)117raSn
Eth = 2 0 - 8
PART 3-3 559
INDIUMAl l curves in Figure 69
Helium 3
In(3He,pxn)113Sn
115 In(3He,p)117mSn
Eth = °
Helium 4
. In(a,pxn)113Sn
115In(a,pn)117mSn
Eth = 1 2 - 4
TIN
Protons/Figure 65
Sn(p,xn)
Sn(p,xn)
Sn(p,xn)
Sn(p,xn)
116Sb
117Sb
1 1 8 m s b
1 2 O l "sb
TELLURIUM
Protons/Fiqure 72
1 2 3Te<p,n)1 2 3 I
E th = 2 - 1 5
12Se(p,2n)123IE t h = 1 1 - 6
Deuterons/Fiqure 71
122TeCd,n)123 I
Eth = °
1 2 2 Te(d , 2 n) 1 2 2 I
E th = 7 - 3
1 2 2Te(d,3n)1 2 1 I
E th = 1 5 " 7
Helium 3
Figure 73
Te(3He,xn)125Xe
Helium 4
Figure 73
Te(a,xn)125Xe
560 ALBERT et al.
IODINE
Protons/Figure 70
127ICp,5n)123Xe
E t h
PLATINUMAll curves in figure 59
194Pt(p,xn) Au
1 QA
Pt(p,xn) Au
198Pt(p,n)198Au
E t h
GOLD
Al l curves in Figure 74
Helium 4
197Au(a
Eth
197Au(a
Eth =
AuCa,
Eth
197Au(a
Eth
,200..,n) Tl
= 10
,2n)199Tl
16.8
3n)198mTl
= 26
,3n)1989Tl
= 26
PART 3-3 561
THALLIUM
Al l curves in Figure 75
Protons
TUp,xn)203Pb
Tl(p,xn)201Pb
nCp,xn>2°°Pb
199Tl(p,xn) Pb
LEAD
Protons/Figure 76
Pb<p,pxn>201Pb
Pb(p,pxn)200Pb
Deuterons/Figure 77
Pb(d /xn)2078i
Pb(d,xn)206Bi
Pb(d,xn) Bi
Helium 4/Figure 78
Pb(a,xn>206Po
562 ALBERT et al.
12-
10-
< 8
"o 6
4-
2-
10 15Energy (MeV)
Boron
Nitrogen
Lithium (VlO)
Beryllium
20
FIG. 1. Thick target yields for the production of nBe for proton reactions on Li, Be, B andN[2}. (1 dis/min = 6.00 X 10l Bq.j
PART 3-3 563
Lithium
Boron
Nitrogen (X10)
Beryllium (X10)
5 10 15
Energy (MeV)
FIG. 2. Thick target yields for the production of 7Be for deuteron reactions on Li, Be, B andN[2).
564 ALBERT et al.
1.75-
1.50-
10 20 30 40
Particle energy (MeV)
FIG. 3. Yield ofnC after irradiation of beryllium with 3He and *He ions [target: Be) [3 ].= 1.00X10°Bq.)
PART 3-3 565
0 5 10 15 20 25
Proton energy (MeV)5 10 15 20 25
Deuteron energy (MeV)
0.0
2.0-
1.5-
1.0-
0.5-
00
B r 3He ,
7/
""yf10 20 30 40 50
o-particle energy (MeV)
0.25
0.20
-0.15
-0.10
-0.05
<s/
sl
o>o
ield
(
>
CO
5 10 15 20 25 30
He ion energy (MeV)
FIG. 4. Yields of nC and 13N after irradiation of boron with protons, deuterons, 3He and *Heions (target: B) [3 ].
566 ALBERT et al.
13
FIG. 5. Production of nC by triton irradiation of a thick, pure boron target. The yield(511 keV annihilation peak) is obtained at the end of an irradiation of 1 h at 1 iiA, and isvariable with the annihilation conditions [4].
PART 3-3 567
<
ofo
1 yi
eld
(
u.o
0.7
0.6
0.5
0.4
0.3
0.2
0.1
on
C + p
1 3 N /
1
5 10 15 20 25Proton energy (MeV)
4.0
3.5
3.0 -
2.5 |
2.0 oTo
1.5 1
o1.0 z
0.5
0.0 0 5 10 15 20 25 303He ion energy (MeV)
5 10 15 20
Deuteron energy (MeV)
0.5
• 0.4
• 0.1
250.0
1.0
0.9
0.8 •
0.3
0.2
<
ield
>.o
% 0.6
s/s
S 0.5°O| 0 . 4«
0.3
0.2 •
0 . 1 •
0.020 25 30 35 40 45
o-particle energy (MeV)
F/G. 6. Yields of nCand 13N after irradiation of carbon with protons, deuterons, 3He and*He ions (target: graphite) [3].
568 ALBERT et al.
3.
oTo
Yie
ld (
0.8 -I
0.7-
0.6-
0.5-
0.4-
0.3-
0.2-
0.1-
0.0-
N + 3He /
/
11 /
1/V
5 10 15 20 25
Proton energy (MeV)
5 10 15 20 253He ion energy (MeV)
30
5 10 15 20 25
Deuteron energy (MeV)10 20 30 40 50
a-particle energy (MeV)
FIG- 7. Yields of nC, 13Nand lsF after irradiation of nitrogen with protons, deuterons, 3Heand *He ions (target: A1N) [3].
PART 3-3 569
tob
Yie
ld (
(dis
/mir
106'
5
2
5
2
104
5
2
1 0 3
14N(d,n)15O
-
i i i .10 15 20
(MeV)
F/G. 8. Thick target yield for the production of ls0 by deuteron irradiation of AW. Theyield is expressed here in disintegrations per minute at the end of irradiation for 1 min at1 \JA for a target containing 10'6g/g of the element in question [5].
570 ALBERT et al.
.a
2
(10
yie
ld
z
3
<_a
'•B
%
>.2
"
10
9
8
7
6
5
4
3
2
1
o(
5
4
3
2
1
0
0 + p
• V/
1 I• 18F / /
7 /
) 5 10 15 20
Proton energy (MeV)
O + d
J13 /
N /
/
/
18F / !F \ / /
•
•
•
20
18
16
14
12
10
8
6
4
2
025
! •
-
-
-
-
-
18
16
14
12
10
8
6
4
2
0
_a.-£?
dis/
(10
yie
ld
U-co
<a.
52
*%
>CO
a.
2O)
o
eld
(1
>•
_
<
is/s
T3
o
TJ
Yie
l
1.0
0.9
0.8
0.7
0.6
0.5
0.4
0.3
0.2
0.1
0 0c
0.6
0.5
0.4
0.3
0.2
0.1
0.0
0 +3He i
: /
/
JI
JrS I
18F / /
5 10 15 20 25 3
He ion energy (MeV)
0 + a /I
118F. /
jI
11
1JII
//
5 10 15 20 25
Deuteron energy (MeV)20 25 30 35 40 45 50
a-particle energy (MeV)
FIG. 9.and *He
Yields of 11C, l3N and 18F after irradiation of oxygen with protons, deuterons, 3Heions [target: AI2O3) [3].
PART 3-3 571
13
FIG. 10. Production ofnFby triton irradiation of a thick A^03 target. The yield (511 keVannihilation peak) is obtained at the end of irradiation for 1 hat 1 uA, and is variable withthe annihilation conditions [4].
572 ALBERT et al.
.a
• D
cno
3.5-
3.0-
2.5-
2.0
1.5-
1.0-
0.5-
0.0
F + p t
I18F /
IJJ
5 10 15 20 25
Proton energy (MeV)
Vh
)
2o
eld
(
>
0.8-
0.7-
0.6-
0.5-
0.4-
0.3-
0.2-
0.1 -
nn
F + d
1
1F ^ /
I1I
JJy5 10 15 20 25
Deuteron energy (MeV)
2cno
Yie
l
0.7-
0.6-
0.5-
0.4-
0.3-
0.2-
0.1 •
0.0
F+a
. y
//
18F /
/
/
/
15 20 25 30 35 40 45
a -particle energy (MeV)
10 15 20 25 30He ion energy (MeV)
FIG. 11. Yield of nF after irradiation of fluorine with protons, deuterons, zHe and AHe ions(target: (CF2jn) [3].
PART 3-3 573
FIG. 12. Thick target yield curve for the l9F fa, n)22Na reaction. Target: PbF2 [6].
574 ALBERT et al.
50 100 150Range (mg/cm )
200
0 2 4 6 8 10 12
Energy (MeV)
14 16
FIG. 13. Thick target saturation activity for the reaction of deuterons on neon to give 18F.Target: pure neon in sealed cylinders at I atmosphere \1\(1 atm = 1.013 25 X 10s Pa).
10 20 30
Energy (MeV)
40 50
FIG. 14. Thick target yields of 28Mg for the reactions oftritons on Mg, Al and Si, and ofoc-particles on Mg and Al [8].
PART 3-3 575
10
10"
10,-7
10-8
10"10
I I I I I [ i
25Mg(<r,p)28AI
5 10E^ (MeV)
15
FIG. 15. Thick target yields for the (a, p) reactions on Mg isotopes. Yield: the ratio of thetotal number of reactions of a given type to the number of incident beam particles, assuming100% abundance for every isotope [9].
576 ALBERT et al.
< „
10'
10 t i t t i t i t I t
10 20 30 40
Energy (MeV)
50
FIG. 16. Thick target yields of 2*Na for the reactions of tritons on Mg, A! and Si, and ofa-particles on Mgand Al [8].
10
0 20 40 60 80 100 120 140 160 180
Incident a-particle energy (MeV)
FIG. 17. Yields of 2SMg, Na, 22Na and 7Be after irradiation of21Al with high-energya-particles [10]. (1 Ci = 3.70 X 1010 Bq.J
PART 3-3 577
10i .
<
O
27AI(a.n)30P
,d)30P
10"
. . . . f . . . . I . . . . I . . . .0 10 20 30 40
Incident particle energy (MeV)
FIG. 18. Theoretical thick target yields of carrier-free 30P for various nuclear processes asfunctions of incident projectile energy [11].
500 -
100 —
2 50 -
_ ' ' ' ' 1 ' ' ' ' 1 ' •28Mg production from thick targets of
P
— c
- / /
/ n
• f / / *
••.I.//./.,..
1 1 |
(Na4P2O7) -
(UiCI)
r (frozen)
(Na2SO4) -
( K 2 C O 3 )
• , 1
10 -
100 150 200Incident proton energy (MeV)
FIG. 19. Thick target yields for the production of 2SMg [12].
578 ALBERT et al.
5 10 15 20
Proton energy (MeV)5 10 15 20
Deuteron energy (MeV)
5 10 15 20 25 30
•'He ion energy (MeV)
10 20 30 40
a-particle energy (MeV)
FIG. 20. (a) Yields for radioisotopes vs proton energy. Curve 1: Cl+p- *Cl; curve 2:
S + p • nCl. (bj Yields for radioisotopes vs deuteron energy. Curve 1:curve 2: S + d-* 34mCl. (cj Yields for radioisotopes vs 3He ion energy. Curve 1: S + 3He~>- 34mC7;curve 2: Cl + 3He ->3iCl; curve 3: Cl + 3He ->• 34mC/. (dj Yields for radioisotopes vs a-particleenergy. Curve 1: « + « - • 34mCl; curve 2: Cl + a-+ 34mCl; curve 3: P + a-*• 34mC/. (Sourcefor all figures: Ref. [13].;
PART 3-3 579
10
- io
i i i i i I r
10,8 . 1 . 1 I I I I I I I4 S 6 7 8 9
E. (MeV!10 11 12 13
FIG. 21. Production of 34mC/ by triton irradiation of a pure S target. The yield (146 ke V) isobtained at the end of irradiation for 1 hat 1 pA [4].
IO-1
u
T 10"J
IO-4
io-s
10 15 20 25 30o-particla energy (M*V)
FIG. 22. Yields of 3iK, 34mO, 72Na and ™Na as functions of the energy at the end of a 15 minperiod of irradiation of NaCl powder [14].
580 ALBERT et al.
10"'
10'
10"
r10
48Ca(p.n)48Sc
63,ulp.nl^Zn
10 15 20
E|ab (MeV)
25
FIG. 23. Thick target yields from the (p, n) reaction measured by the radioactive decay ofthe final nuclide. Targets: Ca, Cu and Zn. The yield is defined here as the number ofradioactive products formed per incident proton upon a thick target composed solely of thetarget isotope [15].
PART 3-3 581
10',-4
10'
10"'
10"
,-5
10-8
10,-9
10-10
»40Ca(«.p)43Sc
10 20 30
FIG. 24. Thick target yields for the (at, n) and (a, p) reactions on Ca isotopes. The yield isdefined as the ratio of the total number of reactions of a given type to the number of incidentbeam particles, assuming 100% abundance for every isotope [9].
582 ALBERT et al.
1010
10
10
10
10
52m,
10
Ep (MeV)
Cr(p,xn)
(1332.5 keV)Ni(p,xn)
Cu(p,n)
(669.6 keV)
Zn(p,xn)
(1039.35 keV)
4 8 w (983.5 keV)Ti(p.xn)
Mn^-Cr(p.xn) (1434.3 keV)5 5Co 58Ni(p.al (931.1 keV)
56CO Fe(p.xn) (846.75 keV)6 1Cu Nt(p.xn) (282.9 keV)51Cr V + p (320.1 keV)
67Ga Zn(p,xn) (93.3 keV)
6 5 Zn 65Cu(p.n| (1115.5keV)
15
FIG. 25. Specific activity, expressed in gamma rays per second, for the thick target yields ofnatural metals (Ti, V, Cr, Fe, Ni, Cu,Zn) at the end of proton irradiation for I h at 1 fiA [16].
PART 3-3 583
10
10" J
.? 10"3J
,0"4J
44m-
51Cr
0 20 40 60 80 100 120 140
Incident ^He particle energy (MeV)
FIG. 26. Thick target yields of*BCr, slCr and major impurities as functions of incident 3Heparticle energy on titanium [17].
584 ALBERT et al.
FIG. 2 7. Thick target yields for the (a, nj and fa, p) reactions on Ti isotopes. The yield isdefined as the ratio of the total number of reactions of a given type to the number of incidentbeam particles, assuming 100% abundance for every isotope [9].
PART 3-3 585
10 1
101 .
b
10', -2 .
10,-3
( a b )
51Cr
O 20 40 60 80 100Incident deuteron energy (MeV)
0 40 80 120 160 200Incident a-particle energy (MeV)
FIG. 28. Thick target yields of chromium isotopes formed by interaction of (a) deuterons withvanadium and (b) a-particles with titanium [17].
586 ALBERT et al.
FIG. 29. Thick target yield for the 51 V(a, n) Mn reaction. The yield is defined as the ratioof the total number of reactions to the number of incident beam particles, assuming 100%abundance for S1V[9].
PART 3-3 587
10.4
,-510
10
10,-7
10,-8
10-9
10',-10 . ,
I I • • I
5CWn)53Fe
10 20
^ (MeV)
30
FIG. 30. Thick target yields for the (a, n) and (ct, pi reactions on Cr isotopes. The yield isdefined as the ratio of the total number of reactions of a given type to the number of incidentbeam particles, assuming that the isotopic abundance is 100% for every isotope [9].
588 ALBERT et al.
10 1
10,-10
FIG. 31. Thick target yields for reactions of a-particles on Mn. The yield is defined as theratio of the total number of reactions of a given type to the number of incident beamparticles [9].
PART 3-3 589
40
FIG. 32. Thick target yield curves for the production of cobalt isotopes by (3He + ssMn)reactions [IS].
590 ALBERT et al.
10
-o
0.1
0.01
100
- 95 mO
4.0 -
1.0
"gDC
20 25 30 35Incident proton energy (MeV)
0.1
FIG. 33. Thick target yield for ssCo given as a function of incident proton energy. Also shownis the per cent total radioactivity of S5Co, S6Co and s2Mn (principal contaminants) vs protonenergy (right-hand ordinatej (EOB: end of bombardment). A natural iron target is used [19].
PART 3-3 591
( a ) io4
5 10 15
Ed (MeV)
10 20 30
Ep (MeV)
10'10 20 30
Ed (MeV)10 20 30 40 50 60
Ep (MeV)
FIG. 34. (a) Thick target yields for enriched targets of ^Fe (98.19%) and s6Fe (99.93%)(evaluated from cross-section data reported in the literature) irradiated with deuterons ^Fand protons s6Fe. (b) Thick target yields for a natural Fe target irradiated with deuteronsand with protons (evaluation) [18].
592 ALBERT et al.
10-4
10
10
-5
10,-7
10
10 '
,-8
10-10
54Fe(a,p)57Co
10 20E„ (MeV)
30
FIG. 35. Thick target yields for the (a., nj and (a, pj reactions on ^Fe. The yield is definedas the ratio of the total number of reactions of a given type to the number of incident beamparticles, assuming that the isotopic abundance is 100% [9].
PART 3-3 593
IO* -
<a.
o
•S 10
" .o°U jJ!
/j- 1
1
/
iI
5 7Nicumulativeyield • '
5 7Ni yield
57Co yield
Cumulative Co yield m
from Ni " S ^ •"*
i i
:o from 5 7Ni
1 1 120 24 28 32 36
Proton energy (MeV)
FIG. 36. Thick target and cumulative yields for the slNi parent (at EOB) and the slCodaughter radionuclides (at tmax= 271.5 h post-bombardment) as functions of proton energy.Cumulative yields were calculated by summing the individual thick target yields, as given inthis figure [20].
594 ALBERT et al.
( a )
_ 5
E
0 10
59Co(3He.n)61Cu
100
50
20 30Incident beam energy (MeV)
40
( b ) -:- 10
oa.2 5
(A):
(B):
(C):
59Co(3He.a>58Co
59Co(3He,nn)57Co
59Co(3He,a2n)56Co
10 20 30Incident beam energy (MeV)
40
FIG. 37. (a) Excitation curve and thick target yield curve for the 3He reaction on cobaltproducing 61Cu. (bj Thick target yield curves for 3He reactions on cobalt producing s6Co,S7Coand s*Co [21].
PART 3-3 595
( a ) - i s
<3 10
S 5
(A): 59Co(a,an)58Co
(B): 59Co(o,a2n)57Co
10 20 30Incident beam energy (MeV)
(A)
40
( b ) 400
300
5 200
o6 100
10 20 30 40
Incident beam energy (MeV)
4 Q
3 2
FIG. 38. (a) Thick target yield curves for a-reactions on cobalt producing 57Co and $sCo.(b) Excitation curve and thick target yield curve for an a-reaction on cobalt producing61Cu [21].
596 ALBERT et al.
10"
10,-5
10,-6
10
10
.7
10,-9
10 10
10 20
. . . . I . . . . I . . . . I . . . . I . . . . I
, (MeV)
30
FIG. 39. Thick target yield for the S9Co (a, n)61Cu reaction. The yield is defined as the ratio ofthe total number of reactions to the number of incident beam particles [9].
PART 3-3 597
10
( a ) ( b )
FIG. 40. (a) Thick target yields for a 99.95% SSM enriched target (evaluation from cross-section data reported in the literature) irradiated with protons, (b) Thick target yields for anatural Ni target (evaluation) irradiated with protons [18].
-100
-50
a.o
£„(MeV)
FIG. 41. Thick target yield curves for 60Cu, 6lCu and "Cu. Target: natural nickel irradiatedwith 4He [22].
598 ALBERT et al.
10"
10,-5
10-6
10-7
10',-8
10,.9
10,-10
l 5 £ W.p) 6 1 Cu
10 20 30
FIG. 42. Thick target yields for (a, nj and (a, p) on Ni isotopes. The yield is defined as theratio of the total number of reactions of a given type to the number of incident beam particles,assuming that the abundance is 100% for every isotope [9].
50,
_ 40
^ 30gu? 20o° 10
10 15 20 25
a energy (MeV)30 35
FIG. 43. Excitation function ( j and the thick target yield ( ) for 62Zn by alphabombardment of natural nickel [23].
PART 3-3 599
10'
10.5
10,-6
10'.7
10-8
10,-9
10,-1010 20 30
FIG. 44. Thick target yields for (a, nj reactions on Cu isotopes. The yield is defined as theratio of the total number of reactions of a given type to the number of incident beam particles,assuming that the abundance is 100% for every isotope [9].
600 ALBERT et al.
10
10-
10
-4
10,.7
10-8
10,-9
10,-10
.6 42n(a,p)6 7Ga
10 20
n(MeV)
30
FIG. 45. Thick target yields for the (a, nj and (a, pj reactions on Zn isotopes. The yield isdefined as the ratio of the total number of reactions of a given type to the number of incidentbeam particles, assuming that the abundance is 100% for every isotope [9].
PART 3-3 601
1000 -
.- 100
10 -
" Zn 4- a
-
/
• \ / ' /
:' V >
6
//
/
/
6 6 G a :
6 6 G e !
r Ga"
f /? ]/r/
'/ / > •
41
- 1
1
-
-
1
20
- 10
30(MeV)
- 1
- 0.1
40
b)10° -
.-• 10 h
10' -
10v
(1)
• /I1
/
/
66Ga
1Zn
f
67Ga
+ di
10 15Ed (MeV)
20
1 0 3
102
101
(2) S
I
,
Zn +i i
i
P
10 20 30
Ep (MeV)
1 0 3
1 0 2
10°
(3)
" /
7 // 6 7 Ga
ICu + a
10 20 30
En (MeV)
FIG. 46. (a) Thick target yield curves for the a bombardment of natural zinc. The ordinatescales for 6iGe and 6SZn (dashed lines) are given on the right, (b) Thick target yield curves forproduction of &1Ga and i6Ga by irradiation of natural Zn with (1) deuterons and (2) protons,and of natural Cu with (3) *He (evaluation from published cross-sections) [24].
602 ALBERT et al.
10'
~ io6
10"
10
(1106.5 keV)
I I I I
10
Ep (MeV)
69Ga(p.n)69Ge
15
FIG. 47. Specific activity for the thick target yield of 69Ge obtained at the end of protonirradiation of GaAs for 1 hat 1 nA [25].
PART 3-3 603
10"
~ 10°
10
100.5 1 2 3Target thickness (g/cm2)
0 10 20 30 40 50 60 64Energy degradation in target (MeV)
FIG. 48. Thick target yields of nuclides produced by the Ge (p, xnyp) reactions. The incidentproton energy is 64 Me V. The abscissas are energy degradations in the Ge target or in the targetthickness (g/cm2) [26].
Range (Mg/cmz) in GeOj3He (upper) 75 100 150 2254He (lower) 601 I 100 120i 150 | 190
20 35 4025 30
E (MeV)
FIG. 49. Thick target yields of 13Se produced by selected nuclear reactions on Ge isotopes [27].
604 ALBERT et al.
10
10"
-3
10,-5
10-6
10.7
10', •8
10-9
i i i I I i r
72Ge(a,n)75Se
7 10 20 30 40
FIG. 50. Thick target yields for fa., n) reactions on Ge isotopes. The yield is defined as theratio of the total number of reactions of a given type to the number of incident beam particles,assuming that the abundance is 100% for every isotope [9].
PART 3-3 605
10'
? 10o
,-3
8 2Se(p.n l 8 2Br\ I
'78S«(p.2n.77
Br
Target: 92.4% 77Se
10
10"
.-3
10 15 20Proton energy (MeV)
25
10'
10"
10-3
o
I 10"
10
( b )
Target: 97.9% 78Se
1 0 ' _
,,-2 U
O
.-3 C
10"
10 15 20Proton energy (MeV)
25
FIG. 51. (a) Yield curves for lbBr and 17Br and i2Br obtained from (p, n) and (p, 2nj reactionson an enriched inSe target, (bj Yield curves for 16Br, 71Br and S2Br obtained from (p, n) and(p, 2n) reactions on an enriched 785e target [28].
606 ALBERT et al.
= 10"* r
40
Incident °He particle energy (MeV)
10 20 30 40
Incident ^He panicle energy (MeV)
a.6
ivity
yie
ldA
ct
1 0 1
10°
1 0 1
10-2
io-3
i n 4
r ( c )
r
• /
- VI
"K,
/
10 20 30 40
Incident He particle energy (MeV)
FIG- 52. (a) Thick target yields for nnKr and other major competing products as functions ofincident 3He particle energy on niSe (enrichment: 96.9%). (bj Thick target yields for nlKr andother major competing products as functions of incident 3He particle energy on 71Se(enrichment 94.4%). (c) Thick target yields for 16Kr, nlKr and ^Kr as functions of incident3He particle energy on natural selenium [29].
PART 3-3 607
•oE
arge
mCO
jra
l10
5
1
0.5
- 0.1
NaBr(p,xn) 77Kr
Kr Br
20 40 60Proton energy (MeV)
80
FIG. 53. Activity yields from a thick natural NaBr target [30].
£
<
o
Z o.i
0.01
68 MeV
90
Outgoing energy (MeV)
80 70 60 50 -
100
10
Y.(O
0.5 1.0 1.5 2.0 2.5 3.0Target thickness (g/cm^)
3.5 4.0
FIG- 54. Determination of the optimum energy region for the production of 15Kr. fa) Thick targetyield of lsKr, (bj contamination of lsKr by 16Kr, and (c) by nnKr vs a natural bromine target thicknessat a constant incident deuteron energy of 90 Me ^[31] .
608 ALBERT et al.
f
<3
-a
et y
iela
rgi
i1-
1 0 3
1 0 2
10
(a)A
/Jt~ /rfi E/-/ i• iI '
10
10"
10 20 30 40
Incident beam energy (MeV)
A = 7 9Br(a,2n)8 1Rb
B = 7 9 B r ( a . n ) 8 2 r r W 8 1 R b ( Q . 3 n ) 8 2 m R b
C =8 1Br(a,2n)8 3Rb
8 1Br(a.n)8 4Rb
E = 79Br(cr,cr2n)77Br
10 '
<
•s i o
(b)
10 20 30
Incident beam energy (MeV)
4 0
A = 8 1 Br(3He,3n)81 Rb+79Br(3He,n)81 Rb
B= 8 1 Br ( 3 He,2n ) 8 2 m Rb
C = 79Br(3He,p2n)79Kr+81Br(3He,p4n)79Kr
FIG. 55. (a) Thick target yield curves for an a bombardment of a potassium bromide targetproducing uRb, i2mRb, S3Rb, mRb and nlBr. (b) Thick target yield curves for a 3Hebombardment of a potassium bromide target producing slRb, B2mRb and ^Kr [32].
PART 3-3 609
100 100
81 n
-
nRb fa
r
! t
100
- 1 _•
-0.1 E
J0.01
81 Rb
0 4 8 12 16 20 24 28Ep (MeV)
0 4 80.01
12 16 20
p(MeV)24 28
5 1 0
ocr
CQ
O2 1
82mRb
-
" /
•Jj V'f/, -,!
- 1
1000 1000
0 4 8 12 16 20 24 28Ep (MeV)
Jo.i
FIG. 56. Yield curves for the production of Rb radioisotopes by proton bombardment ofnatural krypton gas [33]. The dotted line gives the results obtained with the cross-sectioncurves of Lamb [34], while the dashed line gives the results of Acerbi [35]. The vertical dashedline indicates the Q values involved.
610 ALBERT et al.
20 30 40 50 60 70
Incident proton energy (MeV)
80
FIG. 5 7. Thick target yields for an enriched S5RbCl target (99. 78% enriched ssRb) for the(p, pxn) - (p, axn) and (p, xnj reactions. The slRb yield includes contributions of the decaysof 8iSr and slmRb during irradiation; yields of i3Rb and **Rb include contributions from i3Srand **mRb, respectively [36].
PART 3-3 611
^r 100
a.c3a.
>| 50
OIEf -
( a )
//.//
InI /Iill
,A
Ac// E
/ / _ /
/ / 71
r
y B %MV-.2n.8QY
OIcT3 85M,<3 | .e.nl°
7-Y
0 10 20 30 40
Incident beam energy (MeV)
a
o
01> -
targ
eic
k '
si1-
15
10
5
0
A
U
c
D
K
U5Rb(u
87Rb (n
Rb.,,.
( a 7Rb,a.
0 5 « . ( . . .
8 5 Kb(«,
3n)86mY
06m5n) V
..)'mY
3n,°8y
2,,,S7™Y
4n,85Y /
( b )
//
/ // /1 /
/ // A
A
/
A-—.
^ •
30
20 %
oa.
10 ~
10 20 30 40 50
Incident beam energy (MeV)
60
FIG. 58. (a) Thick target yield curves for the 2He reaction on rubidium chloride producingssYy ssmjr Mmr> 87my and 88y ^ Thick target yieid curves for the *He reaction on rubidium
chloride producing SSY, ssmY, """Y, 87mYand SSY [37],
612 ALBERT et al.
104A (555.8 keV)
Zr
Ge (1106.5 keV)
'Tc (765.8 keV)
9 3 m M o (1477.2 keV)9 9 m T c (140.5 keV)
96Tc (778.3 keV)
(328.3 keV]
(909.1 keV)
I96Au (355.7 keV)
(411.8keV)
(765.8 keV)
FIG. 59. Specific activities for the thick target yields of natural metals (Y, Zr, Nb, Mo andPd) after irradiation with protons for 1 h at 1 \iA ((p, xn) reactions) [25].
PART 3-3 613
0 10 20Proton energy (MeV)
0 10 20Proton energy (MeV)
(c )
§ 3
•7" 2
Oa.o 1
10 20Proton energy (MeV)
10 20Proton energy (MeV)
500
030
1000
750
500 ~
250
30
FIG. 60. (a) Excitation function and the related thick target yield of"mTc. The data refer to97.42% enriched 100Afo targets, (b) Excitation functions and corresponding thick target yieldsof**Tc and 9sTc in a molybdenum target enriched to 97.42% 100Mo. (cj Excitationfunction and thick target yield of"Mo for a target of 97.42% isotopically enriched 100Mo.(d) Excitation functions and deduced thick target yields of 93Tc and 96Tc. The data refer to97.427c enriched Motargets. (All of the curves in this figure were plotted using the averageenergy for the excitation function and the incident energy for the thick target yield.) [38].
614 ALBERT et al.
10
10
•T io3
< 10 -
10
. . . . . . . . . J . . . .
9 4Ru
a-reaction /
1/1/if
I \I \
I '/
/ He-reaction
95Ru S
1
J-—cr-reaction
•I• I— He-reaction
ll
97 Ru
He-reaction
10 20 30 40 10 20 30 40 10 20 30 40Incident particle energy (MeV)
FIG. 61. (a) Thick target yields for (a., nj or (a, p) reactions on Mo isotopes. The yield is theratio of the total number of reactions of a given type to the number of incident beam particles,assuming 100% abundance for every isotope [9]. (bj Theoretical cumulative thick target yieldsof^Ru, 95Ru and 91Ru from the irradiation of natural molybdenum with 2He particles (solidlines) and a-particles (dashed lines) [39].
PART 3-3 615
10 :- ( a )
I O - 1 -
ooooooooooo
103Rh(Q.2n)1059Ag
20 40 60
10
10-
b)j o o o o o o o o o
1 0 3 Rh(a,n)
r' L20 40 60
FIG. 62. (a) Thick target yield for the production ofl0S%Ag. (b) Thick target yield for theproduction of 106mAg by irradiation of 103Rh with a-particles [40].
616 ALBERT et al.
10"
10
10"
,.2
I I I I
35 40 45 50 55 60 65
Proton energy (MeVI
10'
10
70
FIG. 63. Thick target and cumulative 91Ru yields as functions of proton energy(target: 103Rh) [41].
10
1 0 '
o
10
10"'
•2
100o
20 30 40 50 60
Proion energy (MeV)
70
FIG. 64. Cumulative yields as functions of proton energy for 101mRh, 101Rh, 100Rh, 10lPd and100Pd. Summation of yields was done from the high to the low end of the proton energy rangecovered in this work, thus resembling the direction of the proton beam through the Rh target [42].
PART 3-3 617
10'
10"
10(MeV)
,116Sb
113m In
'Ag
Cd
110m
(933 keV)
(391.7 keV)
(158.5 keV)(344.2 keV)
(1077.4 keV)
(93.1 keV)Tc (870.9 keV)
] ] ? m Sb (1229.5 keV)1 1 1 m l n (245.3 keV)
n (657.7 keV)
120m,Sb (1023 keV)
15
FIG. 65. Specific activities for the thick target yields of natural metals (Mo, Pd, Ag, Cd, Sn)after irradiation with protons for 1 hat 1 /JL4 (fp, xnj reactions) [25].
618 ALBERT et al.
20 30 40 503He energy (MeV)
FIG. 66. Thick target yields of wIn, noIn and mIn for the Ag + *He reactions [43 ].
2
He porticles on Cd
I 1 1 1 1 1 1
1 1 1 1 1 r 1 l < I
" JSn
7Sn
0 panicles on Cd
1 1 1 _l 1 1 1 1 1
0 2O 40 60 80 100 120 0 20 40 60 8O 100 120 140
Incident particle energy (MeV)
FIG. 67. Thick target yields of il3Sn and lllmSn as functions of incident particle energy inthe interactions of3He and a-particles with natural cadmium [44].
PART 3-3 619
2 io- L
FIG. 68. Thick target yield curves calculated from the excitation functions for a-particlebombardment of enriched cadmium (98.07% n6Cd) [45].
< 10c
i 10
I I I I I 1O 20 40 SO 80 1OO 120 O 2O "O 6O SO 1OO 1Z0 HO
Incident particle energy (McV)
FIG. 69. Thick target yields of n3Sn and nlmSn as functions of incident particle energy inthe interactions of3He and a-particles with natural indium [44].
620 ALBERT et al.
300
200
100
n
(a)^- 70 MeV
^^7 65 MeV
/ / fiO MPV
-
2 3Thickness Ig/cm'l
300
< 200
o
100
Ep = 60 MeV
LiI,CH2 l2— Nal- K l
Thickness (g/cm^)
FIG. 70. (a) li3Xe yield vs I2 target thickness for various incident proton energies. The123/yield (6. 7 h after irradiation) may be obtained by multiplying the 123Xe yield by 0.110.(b) li3Xe yield vs target thickness for various compounds at 60 MeV incident proton energy.The 123Iyield (6. 7 h after irradiation) may be obtained by multiplying the 123Xe yield by0.110 [46].
PART 3-3 621
1010 20 30Incident deuteron energy (MeV)
FIG. 71. Thick target yields of 123/, l22I and I211 as functions of incident deuteron energy on96.45% enriched n2Te [47].
622 ALBERT et al.
10
10'
<
>
-123 :
Jl—a 1-124
• • _ * . 1-130
Te-122:123:124:125:126:128:130:
%2.3
67.311.73.95.75.04.1
1 1 1 1 1 ( 1 1
10 15 20
Proton energy (MeV)
10
10'
! ( b )
>
<
1 0 %
10 15 20
Proton energy (MeV)
FIG. 72. (a) Yield curves for the production of iodine isotopes obtained by proton bombard-ment of tellurium enriched in l23Te. (b) Yield curves for the production of iodine isotopesobtained by proton bombardment of tellurium enriched in 12ATe. The isotopic compositionfor the present work is also shown (details of the experiments cited in the figure can be foundin Ref. [48]/
PART 3-3 623
200
- 100
Te(3He.xn)'25Xe
Te(a.xn)'2SXe
10 20 30Incident beam energy <MeV(
40
FIG. 73. Thick target yield curves for 3He and a-reactions on natural tellurium producing125Xe [49].
20 30£„ (MeVI
FIG. 74. Thick target yield curves as calculated from the excitation functions for a bombard-ment of gold [SO].
624 ALBERT et al.
I 10°
I 10"
10"-2 . ,
201 Pb
203,
10 20 30 40Incident proton energy (MeV)
(a )
50
0.0120 30 40
Incident proton energy (MeV)
FIG. 75. (a) Cumulative yields of™3Pb, 20iPb, 200Pb and 199Pb in the irradiation of naturalthallium with protons, (b) Yields of201Tl (grown-in during a 32 h decay of the separated leadactivities) vs the energies of the incident protons (curve 1). 200Tl impurity as a percentage of20177 activity at varying incident proton energies (curve 2) [51 ].
PART 3-3 625
2 102
104S 50 55
Proton energy (MeV)60 65
FIG. 76. Thick target yields of'201Pb and 200Pb as functions of proton energy (target: naturallead; Pb(p, pxn) reactions) [52].
x 300
( b )
10 20Energy (M«V)
500
loom
X
JZ
a.6
V
Yie
l
500
400
300
200
100
. /
I
: //• /
/
10 20
Energy (MeV)
FIG. 77. (a) Thick target yields for20SBi production (++++). This work: o. (b) Thick targetyields for 201Bi production (++++). This work: o. (c) Thick target yields for 2<>6Bi production(++-I-I-). This work: o [53].
626 ALBERT et al.
T3
FIG. 78. Thick target yields for the production of ™6Po [53 ].
REFERENCES
[1] MUNZEL, H., et al., Karlsruhe Charged Particle Reaction Data Compilation, Physics Data,No. 15, Fachinformationszentrum, Karlsruhe (1982).
[2] SASTRI, C.S., CALETKA, R., KRIVAN, V., Anal. Chem. 53(1981)765.[3] KRASNOV, N.N., DMITRIYEV, P.P., DMITRIYEVA, S.P., K0NSTANTIN0V, I.O.,
MOLIN, G.A., Uses of Cyclotrons in Chemistry, Metallurgy and Biology, Butterworths,London (1970) 341.
[4] BLONDIAUX, G., VALLADON, M., MAGGIORE, C.J., DEBRUN, J.L., unpublished data.[5] ENGELMANN, C, J. Radioanal. Chem. 7 (1971) 89.[6] VALLADON, M., GI0VAGN0LI, A., BLONDIAUX, G., DEBRUN, J.L., unpublished data.[7] NOZAKI, T., IWAMOTO, M., IDO, T., Int. J. Appl. Radiat. Isot. 25 (1974) 393.[8] NOZAKI, T., KURUKAWA, M., KUME, S., SEKI, R., Int. J. Appl. Radiat. Isot. 26
(1975) 17.[9] ROUGHTON, N.A., INTRAT0R, T.P., PETERSON, R.J., ZAIDINS, C.S., At. Data Nucl.
Data Tables 28(1983)341.[10] PROBST, H.J., QAIM, S.M., WEINREICH, R., Int. J. Appl. Radiat. Isot. 27 (1976) 431.[11] QAIM, S.M., OLLIG, H., BLESSING, G., Int. J. Appl. Radiat. Isot. 33 (1982) 271.[12] LUNDQVIST, H., MALMBORG,P., Int. J. Appl. Radiat. Isot. 30 (1979) 33.[13] ZATOLOKIN, B.V., KONSTANTINOV, J.O., KRASNOV, N.N., Int. J. Appl. Radiat. Isot.
27(1976) 159.[14] VANDECASTEELE, C, VANDEWALLE, T., SLEGERS, G-, Radiochim. Acta 29 (1981) 71.
PART 3-3 627
[15] 1NTRATOR, T.P., PETERSON, R.J., ZAIDINS, C.S., Nucl. Instrum. Methods 188(1981)347.
[16] BARRANDON, J.N., DEBRUN, J.L., KOHN, A., SPEAR, R.H., Nucl. Instrum. Methods127(1975)269.
[17] WEINREICH, R., PROBST, H.J., QAIM, S.M., Int. J. Appl. Radiat. Isot. 31 (1980) 223.[18] WATANABE, M., NAKAHARA, H., MURAKAMI, Y., Int. J. Appl. Radiat. Isot. 30
(1979)625.[19] LAGUNAS-SOLAR, M.C., JUNGERMAN, J.A., Int. J. Appl. Radiat. Isot. 30 (1979) 25.[20] JOHNSON, P.C., LAGUNAS-SOLAR, M.C., AVILA, M.J., Int. J. Appl. Radiat. Isot.
35 (1984)371.[21] HOMMA. Y., MURAKAMI, Y., Bull. Chem. Soc. Jpn. 50(1977) 1251.[22] MURAMATSU, H., SHIRAI, E., NAKAHARA, H., MURAKAMI, Y., Int. J. Appl. Radiat.
Isot. 29(1978)611.[23] NEIRINCKX, R.D., Int. J. Appl. Radiat. Isot. 28 (1977) 808.[24] NAGAMA, Y., UNNO, M., NAKAHARA, H., MARAKAMI, Y., Int. J. Appl. Radiat. Isot.
29(1978)615.[25] KOHN, A., Thesis, University of Orsay, 1976.[26] HORIGUCHI, T., KUMAHORA, H., INOUE, H., YOSHIZAWA, Y., Int. J. Appl. Radiat.
Isot. 34(1983) 1531.[27] GUILLAUME, M., LAMBRECHT, R.M., WOLF, A.P., Int. J. Appl. Radiat. Isot. 29
(1978)411.[28] JANSSEN, A.G.M., VAN den BOSCH, R.L.P., de GOEU, J.J.M., THEELEN, H.M.J.,
Int. J. Appl. Radiat. Isot. 31 (1980) 405.[29] YOUFENG, H., QAIM, S.M., STOCKLIN, G., Int. J. Appl. Radiat. Isot. 33 (1982) 13.[30] LUNDQVIST, H., MALMBORG, P., LANGSTROM, B., CHIENGMAI, S.N., Int. J. Appl.
Radiat. Isot. 30(1979)39.[31] QAIM, S.M., WEINREICH, R., Int. J. Appl. Radiat. Isot. 32 (1981) 823.[32] HOMMA, Y., KURATA, K., Int. J. Appl. Radiat. Isot. 30 (1979) 345.[33] MULDERS, J.J.L. Int. J. Appl. Radiat. Isot. 35 (1984) 475.[34] LAMB, J.F., BAKER, G.A., GORIS, M.L., KHENTIGAN, A., MOORE, H.A., Inst. Radiol.
Spec. Rep. Ser. 15 (1977) 22.[35] ACERBI, E., BIRATTARI, C, BONARDI, M., de MARTINIS, C, SALOMONE, A., Int.
J. Appl. Radiat. Isot. 32(1981)465.[36] HORIGUCHI, T., et al., Int. J. Appl. Radiat. Isot. 31 (1980) 141.[37] HOMMA, Y-, ISHII, M., MURASE, Y., Int. J. Appl. Radiat. Isot. 31 (1980) 399.[38] ALMEIDA, G.L., HELUS, F., Radiochem. Radioanal. Lett. 28 (1977) 205.[39] COMPARETTO, G., QAIM, S.M., Radiochim. Acta 27 (1980) 177.[40] OZAFRAN, M.J., VASQUEZ, M.E., de la VEGA VEDOYA, M., NASSIFF, S.J., Radiochem.
Radioanal. Lett. 43 (1980) 265.[41] LAGUNAS-SOLAR, M.C., AVILA, M.J., NAVARRO, N.J., JOHNSON, P.C., Int. J. Appl.
Radiat. Isot. 34(1983)915.[42] LAGUNAS-SOLAR, M.C., AVILA, M.J., JOHNSON, P.C., Int. J. Appl. Radiat. Isot. 35
(1984)743.[43] OMORI, T., YAGI, M., YAMAZAKI, H., SHIOKAWA, T., Radiochem. Radioanal. Lett.
44(1980)307.[44] QAIM, S.M., DOHLER, H., Int. J. Appl. Radiat. Isot. 35 (1984) 645.[45] MURAMATSU, H., NAKAHARA, H., J. Inorg. Nucl. Chem. 43 (1981) 1727.[46] WILKINS, S.R., et al., Int. J. Appl. Radiat. Isot. 26 (1975) 297.[47] ZAIDI, J.H., QAIM, S.M., STOCKLIN, G., Int. J. Appl. Radiat. Isot. 34 (1983) 1425.[48] VAN den BOSCH, R.L.P., et al., Int. J. Appl. Radiat. Isot. 28 (1977) 255.
628 ALBERT et al.
[49] HOMMA, Y., MURAKAMI, Y-, Int. J. Appl. Radiat. Isot. 28 (1977) 740.[50] NAGAMA, Y., NAKAHARA, H., MURAKAMI, Y., Int. J. Appl. Radiat. Isot. 30 (1979) 669.[51] QAIM, S.M., WEINREICH, R., OLLIG, H-, Int. J. Appl. Radiat. Isot. 30 (1979) 85.[52] LAGUNAS-SOLAR, M.C., LITTLE, F.E., JUNGERMANN, J.A., Int. J. Appl. Radiat.
Isot. 32(1981)817.[53] WASILEVSKY, C, de la VEGA VEDOYA, M., NASSIFF, S.J., Radiochim. Acta 27
(1980) 125.
Part 4
PHOTONUCLEAR ACTIVATION
4-1. PHOTONUCLEAR CROSS-SECTIONS
B. FORKMAN, R. PETERSSONDepartment of Physics,University of Lund,Lund, Sweden
Abstract
PHOTONUCLEAR CROSS-SECTIONS.A compilation is given of photonuclear cross-sections in the giant resonance region.
Special reference is made to applications in activation analysis.
1. INTRODUCTION
In the giant resonance region (10-25 MeV), the most probable result ofphotonuclear absorption is the emission of a single neutron, but other processesmust also be considered, such as the emission of gamma rays, the emission ofmore than one neutron and, particularly for light nuclei, the emission of chargedparticles. Medium and high energy photon spallation yields are systematicallytreated in Ref. [1].
2. BREMSSTRAHLUNG REACTION YIELD
Since there exist no intense monochromatic photon sources, the brems-strahlung beam, obtained when energetic electrons from electron accelerators hita target, is used as the photon source in almost all photoactivation studies. Theenergy spectrum of the photons in a bremsstrahlung beam from a thin target iswell known [2].
The bremsstrahlung beam has a continuous photon energy spectrum. Letn(E, Eo) dE be the number of photons with energies between E and E + dE perunit radiation thickness per second in a bremsstrahlung beam, where Eo is themaximum photon energy. The energy content of the beam in the sample is then
U(E0)= / En(E,E0)f(E)dE (1)
where f (E) is a correction factor which accounts for the distortion of the brems-strahlung spectrum by the effect of photon absorption in the machine target, inthe walls of the accelerator chamber and in the sample.
631
632 FORKMAN and PETERSSON
TABLE I. ENERGY CONTENT OF ANUNDISTORTED BREMSSTRAHLUNG BEAM [3]
Eo
(MeV)
En(E,E0)dE
(MeV)
10
13
16
19
22
27
32
36
44
52
03.554 88
04.786 41
06.046 65
07.327 88
08.625 22
10.814 70
13.029 99
14.814 54
18.416 18
22.047 27
TABLE II. ENERGY SPECTRUM OF UNDISTORTEDBREMSSTRAHLUNG BEAM $ = En(E, Eo)(the table values are 10s times too high [3])
E ® E © E ® E « E «
(MeV)(iOMeV) (MeV)(13MeV) (MeV) (16MeV) (MeV)(19MeV) (MeV) (22 MeV)
1 0
0 9
o a0 7
0 6
0 5
0 k
0 3
0 2
0 1
0 0
>2 9 3 3
6 k 2 6
2 6 6 0
7 0 6 3
0 92 6
k 8 2 1
9 0 8 5
3 9 5 9
9 6 2 9
S( 2 5 2
k 0 1 0
1 3
I 2
1 1
1 0
0 9
0 8
0 7
0 6
0 5
0 k
0 3
0 2
0 1
0 0
0 2 8 1 k
16 2 3 9
2 2 2 7 1
2 6 2 2 2
2 9 3 2 1
3 2 0 9 3
3 k 8 2 9
3 7 7 2 0
k 0 9 0 0
k k k 6 9
k 8 5 0 k
5 3 0 6 8
5 8 2 1 5
6k 0 1 0
1 6
1 5
1 k
1 3
1 2
1 1
1 0
0 9
0 8
0 7
0 6
0 S
0 k
0 3
0 2
0 1
0 0
0 2 7
1 6 1 >
22 1
2 58
2 8 6
9
0
5
3
6
3 0 9 8 5
3 3 0
3 S 1
3 7 2 <
3 9 5
k 2 0
k k 8
k 7 9
5 1 k
5 52
5 9 k
6 k 0
1
6
9
J
5
5
k
7
6
0
c
9
a7
6
S
k
3
2
1
0
9
8
7
6
5
k
3
2
1
0 0
0 2 ( 8 7
1 6 0 8 0
2 2 0 2 k
2 5 7 3 1
2 8 3 8 6
3 0 k 7 6
3 2 2 ( 2
3 3 9 0 7
3 5 5 1 9
3 7 1 7 6
3 8 9 3 5
k 0 8 3 8
k 2 9 1 8
k 5 1 9 8
k 7 7 0 0
5 0 k 3 8
5 3 k 2 6
5 ( ( 76
6 0 2 0 0
6 k 0 1 0
2 2 0 2 6 k 9
2
2
1
1
1
1
1
1
11
1
1
1 6 O k 0
0 2 1 9 8 1
9 2 5 ( 6 1
) 2 8 2 5 0
7 3 0 2 2 9
i 3 1 8 5 2
5 3 3 2 7 5
3 k 6 0 1
! 3 5 9 0 5
! 3 7 2 3 9
3 8 ( fc 3
1 k 0 1 k 6
0 9 k 1 7 7 2
0 8 k 3 5 3 9
0 1 k 5 k 6 1
0 6 k 7 5k 8
O S k 9 a 1 2
0
0
• 5 2 2 5 8
S k 8 9 5
0 2 5 7 7 2 8
0 6 0 7 6 k
0 0 6 k 0 1 0
PART 4-1 633
TABLE II (cont.)
(MeV)(27MeV) (MeV) (32 MeV) (MeV)(36MeV) (MeV) (44 MeV)E ©
(MeV)(52 MeV)
2
2
2
2
2
2
2
1
1
1
1
1
1
1
1
1
1
0
7 0 2 6 0 to
6 1
5 2
to ;
5 '
15
3 2 o
2 3 01
0
9
87
6
5
to3
2
1 h
0 I
9
0 8 >
0 7 I
0 6
0 S
0 to
0 2
0
0
1
0
1
2
3
to
9 7
to 9
2 0
7 0
6 85 6 3
0 5
! 9 1! 9 \
5 8 5 5
6 8 2 0
7
8
9 1 3
1 5 5
9 9 6 t o
1
2
3
5 1
• 2 8
) 0 3
S 2 8 3
6 8 7 3
8
> 0
2
to
8
1
to
S7 7
• 0 1
to 7
1 8
> to 8
1 1
) 1 0
3 2
3
3
I0
2 9
2
2
07
2 6
2
2
2
5
to
3
2 2
2 1
2 0
1
1
1
1
1
1
1
1
1
1
0
0
0
9
8
7
65to1
210
9
7
6
0 5
0
0
0
0
0
to3
210
0
1
2
2
2
33
3
3
J
3
3
3
3
3
3
3
tototototototo
2 5
5 9
1 9
5 6
B 10 0
1 to
2 6
3 6
to to
5 2
7
7
3
1
6
38
to
2
8
7
6 0 2
6 7
7 5
8 2
3
3
3
) 3
6
to 2
21
2 2 8
0
2 6
2
2
5 2
1
> 1
J 1
S 9 1
0 1
8 3
9 0 9 6
9 9 5 8
0 8
1 8
2 9
7
S
0
to 0 2
S 2
6 to
7 8
5 0 8
5 2 to
5
5
> 1
1
S
[
5
9 0
to
1
2
2
5 9 1
5 7 7
5 9 7
i
6
1 8
5
S
9 9
7
to
to 0 1
»
)
to2
0
8
6
to *
2
0
8
6
to20
1
56
7
8
0
1
3
S 5 to
9 3 5
1 7 8
to 7 9
0 5 7
3 1 5
5 6 8
8 6 9
3 0 8
9 3 1
7 7 1
5 8to 9
8
0
3
6
0
to
1 8 2
7 1 2
6 5 7
8 1 (
2 6 5
0 1 0
toto
to
3
3
3
3
to
2
0
8
to
2
0
2 8
2 6
2 to
2 2
2
1
1
1
1
1
0
8
6
to20
8
6
to
2
0
0 2 5 2 7
2 1 9 3 8
2 8 2 2 to V
3 1 5 3 to
S to 9 3 1 *
3 5 9 9 0
3 6 9 0 9
3 7 7 9 7
3 8 7 2 0
3 9 7 2 5
to 0 8 to 1
to 2 0 9 0
to 3 to 8 9
to 5 0 to 6
to 6 7 7 J
to 8 6 7 to
5 0 7 5 7
5 ) 0 2 5
5 5 to 8 2
5 8 1 2 9
6 0 9 7 1
6 to 0 1 0
2
0
8
6
2
0
8
6
to
2
0
! 8
6
! to
2
0
8
6
to
2
0
8
6
2
0
0
2
2
2
1
8
3 1
3
3
3
3
3
3
3
to
to
tototototo
to
to
5
6
7
8
8
9
0
1
2
3
to
5 09 k
2 7
6 1
9 6
9 3
7 I
k 0
0 7
7 6
5 0
3 2
2 2
2 3
3 5
5 8
5 9 3
7 k 1
9 0 1
5 0
5
5
2
to
5 6
83
3
3
7
6
J
2
0
1
to
2
9
6
2
3
6
2
7
7 5 3
6 2
6 2
7 6
1
3
2
6 1 to 5 k
6 to0 1 0
We define the number of equivalent quanta Q by
Q = — U(E0)b0
(2)
i.e. Q is the number of quanta with energy Eo which have the same energy contentas the bremsstrahlung beam and we define the cross-section per equivalent quantum,oq , by
c0
/a(E)n(E,Eo)f(E)dE
<7q(E0)=- (3)
634 FORKMAN and PETERSSON
- n l E . E 0 >
UJ
cr, I E )
o-,(E0) _
IE)
1.0
UJ
0.5 -
E, EM Eo E2
Photon energy E . brems. max energy Eo
FIG. 1. Energy variation of cross-sections for a typical photonuclear reaction and bremsstrahlunggamma source intensity.
The bremsstrahlung reaction yield measured in monitor response units can bewritten as
y(E0) =
a(E)n(E, E0)f(E)dE
U(E0)R(E0) E0R(E0)(4)
The monitor measures only some part of the energy content of the beam and thusR (Eo) gives the sensitivity of the monitor for an Eo bremsstrahlung beam.
While f(E) and R(E0) are quantities specific for a particular laboratory,n(E, Eo) has been tabulated for bremsstrahlung spectra.
In Tables I and II, the energy content and the energy spectrum of anundistorted bremsstrahlung beam for different end-point energies in the giantresonance region are given. It is easy to obtain the photon spectrum from Table IIby dividing the energy spectrum value with the photon energy E.
It is possible to calculate approximately the induced activities of photonuclearreactions, replacing the energy integral in Eq. (4) with a simple summation:
y(E0) =U
(5)
where the laboratory factors f(E) and R(E0) have been neglected (see also Fig. 1).
PART 4-1 635
3. COMMENTS
In the graphs that follow, (7, n) cross-section curves are given which aresometimes complemented with cross-sections for other types of reactions.Preference has been given to monochromatic photon data (marked 'Mono')when available. As a complement, and as a comparison, continuous photon data(marked 'Brems') are also given. For many nuclei equivalent data exist fromseveral laboratories. These are given without preference for comparison. Theseparation energies of particles or groups of particles have been taken fromRef. [4] and are given in MeV. Decay data are taken from Ref. [5]. For furthercross-section data and more detailed information it is possible to refer to thePhotonuclear Data Abstract Sheets, now published in separate volumes by thePhotonuclear Data Center of the United States National Bureau of Standards,Washington, D.C. [6]. We also refer to the photonuclear cross-section atlas formonoenergetic photons compiled by Berman [7]. The survey of literaturepertaining to this compilation was concluded in January 1984.
ACKNOWLEDGEMENTS
Financial support from the National Institute of Radiation Protection,Sweden, is gratefully acknowledged. The authors also wish to thank Boel Forkmanfor her careful preparation of the graphs.
REFERENCES TO SECTIONS 1 THROUGH 3
[1] JONSSON, G.G., LINDGREN, K., Phys. Scr. 7 (1973) 49.[2] SCHIFF, L.I., Phys. Rev. 83 (1951) 252.[3] PENFOLD, A.S., LEISS, J.E., Analysis of Photo-Cross Sections, Physical Research
Laboratory, University of Illinois (1958).[4] WAPSTRA, A.H., BOS, K., At. Data Nucl. Data Tables 19 (1977) 177.[5] Table of Isotopes (LEDERER, CM., SHIRLEY, V.S., Eds), 7th edn, Wiley-Interscience,
New York (1978).[6] FULLER, E.G., GERSTENBERG, H., US National Bureau of Standards, Washington, DC,
Rep. NBSIR-83-2742 (1983).[7 ] BERMAN, B. L., At. Data Nucl. Data Tables 15(1975)319.
636 FORKMAN and PETERSSON
4. CONTENTS LIST OF GRAPHS
Element Page Element Page
123456789
1011121314151617181920212223242526272829303233343738
HHeLiBeBCN0FNeNaMgAlSiPSClArKCaScTiVCrMnFeCoNiCuZnGeAsSeRbSr
Hydrogen 637 39 YHelium 638 40 ZrLithium 642 41 NbBeryllium 649 42 MoBoron 650 45 RhCarbon 652 46 PdNitrogen 654 47 AgOxygen 656 48 CdFluorine 659 49 InNeon 660 50 SnSodium 661 51 SbMagnesium 662 52 TeAluminium 666 53 ISilicon 668 55 CsPhosphorus 671 56 BaSulphur 672 57 LaChlorine 673 58 CeArgon 674 59 PrPotassium 675 60 NdCalcium 676 62 SmScandium 678 63 EuTitanium 680 64 GdVanadium 682 65 TbChromium 684 67 HoManganese 686 68 ErIron 687 71 LuCobalt 688 73 TaNickel 690 74 WCopper 692 76 OsZinc 696 79 AuGermanium 698 82 PbArsenic 702 83 BiSelenium 703 90 ThRubidium 705 92 UStrontium 706 93 Np
Yttrium 708Zirconium 712Niobium 719Molybdenum 720Rhodium 726Palladium 727Silver 728Cadmium 730Indium 732Tin 734Antimony 743Tellurium 744Iodine 746Caesium 748Barium 750Lanthanum 753Cerium 754Praseodymium 756Neodymium 760Samarium 766Europium 772Gadolinium 774Terbium 776Holmium 778Erbium 780Lutetium 783Tantalum 784Tungsten 786Osmium 788Gold 792Lead 794Bismuth 798Thorium 800Uranium 802Neptunium 806
Hydrogen
1000
500
ZOO-
100
50
21
3 S
1 Mono
\
10 20
EY
80Ar46
\ '$ZSO 100
(MeV)
o(r,pl with different theoretical estimates
H
CN
GPG2N •
GNP •
G2P *GA «
» - 1 ( 9 9 . 9 9 ) A
1 2 .I p
p
II
=
2
2
2
2 (O.
S
10.61
015)
mln, 3
A =
6.3
' 8.5
8.5
8.5
M
3 (»)
s10.61
s10.61
min, 3
min, 3"
0
(mb)
3.2
2.1.
1.6
0.8
— " I • • • • - •
a)-
0
(mbl
1.6
12
08
0.4
0
I ' i
-
if
P
bl "
"1 . 1 .
0
(mbl
1.6
1.2
0.8
O.i.
, 1 1 , - — • . • | -
-
-
l7.nl,' ',<7.2nl . i
1 1 •
Cl
-
i »
0 6 12 16
Ey (MeV)SH Mono 81Fa1
21.
a) o(Y,ntlb) o(Y,nlc) o(Y,2n)
with differenttheoreticalestimates
>
5
ON
J
00
Helium0
(mbl
a
(mbl
a
(mbl
3.2
2.4
1.6
0.8
1.6
1.2
0.8
0A
1.6
1.2
0.8
0.4
0
I I
-
/'£•—-
(T.dlC '<-r.nl i
-
-
V
h.d i ' (T.nl ,
-
w•(
1 ' 1 •
al "
i '
bl .
-
-
i . i .
cl 1
-I . I .
• O(Y ,n) compared w i th
O 74Be1 (Ntonol, —63Go13, 6SFe5 (Brcmsl61Ge1 (nremsl
0 6 12 18 21.
EY (Me\O
'lie Mono 81Fa1
ai o(Y,nt
b) o(Y.d)
cl o(Y,n)
with different
theoretical
estimates
O?8
>
3O.• omH
enO
5 10 15
EY (Me\O
'He 79Sk101
(inbi
32 31.
"He Mono 71Be1
o o(r,d) inverse reaction
-n-6SFeS, • 71Wo8, X 7)Ku5,
• 73TH3, T 74Ma5, ---70Ba1
O(Y ,p) inverse reaction 70MeS
O(Y ,n)
(1 )"0.5
0
1.5
(mb) «
0.5
0
1.5 ro
(mb) <••
05
020
/
/
t
I1
- ii.-i N
. 1
M. ^
. (
' t (•
il ''I i- *
" I ' , 1
IT P") h.2M
**«
• • [ • • I
a) .
b) •
•J r"
cl
30 40
o
(mbl
1.6
1.2
o.e
0.4
a) ft
/I/7
I J/ \
hby
\pI
20 24 28
EY (MeV)
32
"He Mono 80Be1
"He 80Bel6
O(Y ,n) theoret ical cross-sect ion:
a) based on the CCRM-I spectrum
b) based on the CCBM- 11 spectrum
• data from 74Ch5 (Mono)
• data from 72Do8 (Mono)
o
2
Sa•nmin5800(/>O
ASIFel, ~ 66Fe7, * 71Be1
and V 63Zu1 (inverse reaction)
b) X °(Y»no) compared with
fc72BeS, O 75Ir16, a 73Ma13
c) X O(Y >'H) compared with
• 68Go13, A 78Ar17,
• 77Ba7, • 72Do8
"He 81Ci45
Best estimates of the total cross-section data of
a) O(Y ,p)
b) o(Y.n)
from 80Be1 (Mono!
and 81Wai (inverse reaction)
7U 28 32
Ey (MeV)
"He 80Be16
O(Y,p) theoretical cross-section:
a) based on the CCRM-I spectrum
W based on the CCRM-II spectrum
• data from 70Me5(inverse reaction)
JO
He
GHCPG2NCNPG2PGA
A =
7.75.5»7.77.7»
3
H
s
s10
(0.
.61
00011)
mln, 0"
A =
20.619.828.326.128.3«
4
S12*S10
(100)
.3H6y, B"
.61 mln, 6"
Lithium
a
(mbi
1.6
1.2
0.8
0.4
00 M
0
(mb)
1.6
1.2
08
F
a)
b")
8 12 16 20 24 28 32
120
dodtt 80
(ub/sr)40
0
0.60.4
*° 0.2dn 0
(gb/sr) o.z0
-0.2
. , 1 1 , M b) •
c). . ' i p 1 i i , i .
12 16 20
EY (MeVl
6 l.i Brems 79Ju4
a) Ao °(Y,p)b) a , o(Y,p)
MeV
TlO
2
so
o
'Li Mono 75Be6 , 65Be8
dodn
(nb/srl
e
6
4
2
Q
albic)
Li
°(Y,n
o(y,n
o(y.2n
\
5
Brems
l
+o(y,pn)
l+o(Y.p2n)
LVX10 15
Ey (MeV)
79Ju4
20 25
Ey (MeV)
6Li Brems 79Ju4
>7)
8=90 MeV o(Y,a) 6=90" MeV
ast
do «o
dft 100
(ub/srl 60
6 0
40
20
18
I,K
22
\
bl
\ .
TOs,
(pb/sr)
22 26 30 3* 18 22 26 30 3t
EY (MeV)
6 Li Brems 79Ju4
al 8=90°o(Y,tl nm r L X = 3 5 M
bl AO o ( Y , t l
c) A1 o ( Y , t l
dl A2 oCy. t l
- ^ (»,£)- £ /(,(£) (cos 0)
-.<0<£)[l+j>,(EI/;(coS(x]. ' | , i Mono 75Be6
blcl
1.5
1.0
0.5
1.5
(mbl1.0
0.5
1.5
0.5
- * . • • * — - • • ' — i — * • — - 1 —
al
• I - - I " . .
bl
'.1 •
c l
22 26 30
z3a.
M
enVIOZ
(MeV)
do
dn
100
(pb/srl 50
An
dn
(pb/srl
do
dn(pb/srl
0.6
0.40.2
0.2
-0.2
\
1
» '
a)-
\ •
,illhlU 1
cl •
111
' L i
a l
blc l
15
EY
Brems
Ao
a i
a 2
o ( Y ,
O ( Y ,
O ( Y ,
20
• (MeVI
79Ju4
pi 0
Pi
Pi
25
do
dn(pb/sr)
do
dn
(pb/srl
do
dn
{pb/srl
to
20
ft
1.0
0.5
00
-0.5
-1.0
'••I
ii
-
11 i
1
' . "
' , 11
t- al
+ ++ '"""l" „, + '
bl .
M i l l l H I 1 ' 1 •
• I l j | l | | l l | | h .
12 H 16 18 20 22
EY frfeVl
' l . i Brems 79Ju4
al Ao o(Y,dl E =28MeVmax
- | - Results from 75De14
bl ai o(Y,dl
cl a2 o(Y,d)
99
646 FORKMAN and PETERSSON
' i
• * 9
D D O D
< <
'n 2
Ov. ° «* -*
7Li Brems 79Sk1
o triton data 9=90°X alpha data
— cluster theory T30C 3 capture data from 61Gr16
4 6 6 10 12 14 16
Ey (Me\T)
79Sk1
Even Legendre coefficients from leastsquares fitting of the data to
Dashed Line indicates the E2 strength
in the a-Jll cluster model of 79Sk1.
L i
GNGPG2NCMPC2PGA
A = 6 (7.5)
5.7 »1.6 •
27.2 "3.7 S
26.1 •1.5 S
A
710121133
2
S
.3
.0
.9
.8
.5
.5
7
S0»»it
12
(92.5)
.8081s, B"
.316y, 8"
79Sk1
Odd I.egendre coefficients.Known negative parity statesin 7Li are indicated.
"8
w
Beryllium
Be
CNGPC2NGNPC2PGA
A =
1.716.920.618.929.32.5
9
6053S»«
(100)
•7E-173,.8M0s,.29d, EC
2a8"2a
a
(rabl
(mbl
'Be
a)
blc)
Mono
o(Y,nl
o(Y,nl
O(Y ,nl
7SKnS
• o(Y(pn) + 2o(Y,2n)
+ o(Y,pnl+2o(Y,2nl
+ o(Y,pnH2o(Y2n)
0
(mb)
751 Iu5
72Th5
7
6
5
4
3
2
1
026 28 30
EY (MeVI
32 34 36 38
650 FORKMAN and PETERSSON
I
oa:
12 I t 16 18 20 22 24 26
EY (MeVl
l l B Brems 73I Iu5
o(Y,n)+o(Y,pnH2o(Y,2n')
B A = 10 (20) A = 11 (80)
8.H 8.5E-19s, p2a 11.5 SCNCP 6 . 6 SG2N 27.0 0.772s, 8*2aCNP 8.3 6.7E-17s, 2aC2P 23.5 0.811s, B"2aGA 4 . 5 S
11.2 1.6E+6y, 8"19.9 8.5E-19s, p2a)8.0 S30.9 0.1783s, 8 " , 8"n
8.7 S
1.0
d_? 0.5
Cub/sr)
10 15 20 25E Y (Me\O
10B Brems 78Ta41
a)
do3n io
( ub / s r l 5
010 15 20 25
EY (MeVl
1 1 B Brems 78Ta41
(Y.do)
Carbon
22 24EY (Me\T)
l 2 C Mono 75Be6 , 66Lo1
o(Y,nJ
26
6
0
Cmb)1-
2
0
1
/|1I1
/
1 ft
h
ri'4'i'i "Aijiii
Hi
•1 1 II 1 1 1 1 1
A 1 1 ill/H i . " I1!
«(W) 22 26 30
Ey (MeVl
a °
(mbi 4
2
0
8
6o
Cmb) 4
2
0
0.8
0.60
(m!>) «•*
0.2
0.0
T f\ :
• • /
"i—I—1—I—1—I—1 X 1—I—I—I—1—I—1—I—r-
blX
i-y
c)
IT. PA) T T IT. 1"!
4 8 12 16 20 24 28 32 36
EY (Me\0
ON
to
11O
WHtn
IZ
13C Mono 79Ju1
2C Mono 75Be6 , 66Ri1
a) oC
bl of
c l o CY , 2nl+o (Y ,p2nl
(mb)
26V. 26
EY (HeVO
*C Brems 76Ca1
• o(Y,pl assuming ground statetransitions only.
Theory:
71Bi13
72Ms8
72Bi5
73Ms5
73Be142
73Ms4
13C
IIIf
Brems
o(Y
O( Y
O(Y
.Pi
.Pi,Pl
83Zu1
64De18
57CO1
o 6(mbl ,
u2
020 22 24 26
EY (MeV)
A = 12 (98.89) A = 13 ( 1 . 1 D
GN 1 8 . 7 2 0 . 3 8 m l n , B \ EC M.9 SGP 16.0 S 17.5 2 .03E-23, 0 " , B"aG2N 31.8 19.151s, B* 23.7 20.38 rain, B \ ECGNP 27.1 S 20.9 SG2P 27.2 1.6E+6y, B" 31.6 13.813, B", 6"oGA 1A 6.7E-173, 2o 10.6 S
"0
en
3 -
Nitrogen
(nfci
10 12 H 16 18 20 22 24 26 28 30
(mb)
Cmb)
(mb)
"N Mono 75Iic6 , 70Bo1
12 16 20 1U 28
EY (Me\O
^N Brems 83Ot47
c l l " N ( Y , P 7 S S M e V ) l I C
l
o2za
w8
(mbl
16
8
0
- a l •
li 1
Mi ^i.
(mbl
16
8
•
- J\Fl£n)
1
T(T. 2n|
bl -
1 ll'll'l
(mb)
u
2
0
-
-
T IT.")I
/W'lf(7.2nl
1 1
cl
-
I" ' ' I I ,• I ' l ' l . l
1 1
10 15 20 25 30 35
EY ( M C V )
Mono 82Ju1
10 15 20 25
EY (Me\D
' "N Brems 78Ta41
A = (99.63) A = 15 (0.37)
CN 10.6 9.963 min, B*CP 7.6 S
10.8 S10.2 5.73OE+3y, 0 '
1 6 *7 S 5 . 7 3 3 y ,
C2N 30.6 1.O95E-2S, B*. S*a 21.1 9.963 mln,8CNP 12.5 S
G2P 25.1 2.03E-23, B", B"aGA 11.6 S
18.1 S31.0 1.733E-2s, B", B"n11.0 S
al c(Y,nl+ o(Y,pnl + o(
bl oCY.nltoCY.pnl + oC
cl o(Y,2nl+o(Y,p2nl
,2nl
Oxygen
(mb)
15
" 0
a)
Mono
20
EY
83Be1
4 o(y.1n)
25(MeV)
30
— o(Y,1nl combined resul t from
64Br1 and 80Ju1
o(Y,1nl 75Kn9
10 • o(Y,1n)
O o(Y ,1n) 82Ca5
— o(Y,1n1 74Ve5
o
(rab)
6o
(mb) 4
o
(mb)
1 80 Mono 79Wo1
a) O(Y ,p)
c) o(Y,2n)+o(Y.p2n)
\—i—I «—1—I
a)
'VI |
Tll.nl Tlr.3"l T|,.p) TlT.3"1 '
I I I I I I I I I I I I I I I I I
Tl7.nl T(T.*>> Tlr.pl T <7.J"I
-+-t-t-HH-i I i I i I i I i I i
TlT.2"! Tlr.Pl T It.I
10 K 18 22 26
EY (Me\0
30 31 38
•nOjo
O
PIwjoCO
O
160
do 12°
dn
(ub/sr)80
• ' V I )ij I l I12 16 20 2t 28 32
Ey (Me\O
" 0 Brems 79Jo1
E . 9x
for (Y,n
1 ( 0 Brems 82Ba5
lilt O(Y,P)
O(Y ,p) 79Wo1
5
- J
O NLAOO
(mbf0.6
01.
0.2
ft
—T—
•1-
-
1
I
1 ' 1 ' '
-
1 .
' • • • • . .
1 . 1 '. • . . .
23 25 27Ey (Me\T>
" 0 Brems 82Ba5
O(Y ,d
mb)'0.3
0.2
0.1
Q
- ^
-
21
" 0
i i 1 1
^* ' •l l i ' i' - >
22 23 24 25EY (Me\O
Brems 82Ba5
connects data points O(Y , t )
from 24 MeV measurement.
o(Y,t) from 32MeV
measurement.
20 22 24 26
E Y (MeVI
l e O Breras 82Ba5
El
E2
0
CMCPC2NCNPC2PCA
A =
15.712.128.923.022.3
7.2
16
1S
70S5S
(99. 76)
.221E*2s, 8 \
.59s,
.73OE
8'
+3y, B"
A =
EC IJ.113.819.816.325.3
6.M
17
S7.1.s2.S
(0 .
13s,221E
15s,
04)
B", B"a+2s, 8*.
8"
A =
8.015.9
EC 12.221.829.1
6.2
18 ( 0 .
S4.17s,S7.13s,0.75s,5.73OE
20)
B",
B",B"n
•3y,
B"n
8" a
B
3ns>zai)mHm
cnOZ
Fluorine
EY (MeV)
F Mono 74Ve5
• O(Y ,nt)
* o(Y,2n)+o(Y,p2n)
(rabl
l ' F Brems 83Ke36
"H. <<Y,pol
II o(Y,pi)
F
GNGPG2NGNPG2PGA
A =
10.18.0
19.616.023.9
4.0
19
1.S
61.S4.S
(100)
O97E+2 rain, B\
50s, B*
174a, B", B'n
EC
>
ON
Neon
(mbl
(mb)o
,'v20 24
Ey (MeV)
20Ne Brems 81A15
28
Mono 74VeS
al Ne natural
• o(Y,n)+o(Y,pnl
A o(Y,2nl+o(Y,p2n)
bl " N e
A oCY,2n)+o(Y,p2n)
•nO
Zvaa.
m
C/l
OZ
20 22
EY (MeVl20Ne (e.e'pl 620n1
(Y,p) 6=76°
Ne A = 20 (90.51) A = 21 (0.27) A = 22 (9.22)
GN 16.9 17.22s, B*, EC 6.8 S 10.1 SGP 12.8 S 13.0 11.00s, B~ 15.3 4.35s, $"G2N 28.5 1.67s, 0* 23.6 17.223, B \ EC 17.1 S-CNP 23 .3 1.908E+2 n i n , B*, EC 19.6 S 2 3 . 1 1 1 . 0 0 s , B"G2P 20.8 S 23.6 26.76s, B" 26.1 13.5s, B"GA 1 .7 S 7 . 3 S 9 . 7 S
Sodium
(mb)
29
a l Na Mono 74Ve5
A o(Yf2n1*o(Y,p2n)
Na
GNGPG2NGNPG2PGA
A =
12.18.823.519.221.110.5
23
2S22S1S
(100
.602y
.17s,
.35s,
.0)
, B*, EC
8*
B~
o
(mb)
0
Onb)
a
fmb)
16
12
4
0
16
12
A
1,
Q
2
1
HI*
j,'!
i
[Jn)
n |, 1l| 1. l l l l l l> 1',>,,"/'
1
uu'i i|,u'n<iV' ' V '
,1
a)
«l
'l'1 '
b)
•i'V
l.'l"1
2 16 20
EY (Me\O
2>Na Mono 71A11
a) o(Y,n t l
bi o(Y,n)+o(Y,pn1
c) o(Y,2nl«)(Y,p2n) O
Magnesium
(mb)
20 22 24 26
Ey (Me\O
21lMg Mono 75De6 , 71Fu1
o(Y,nl+o(Y,pn1
(mb)
20
10
a)
t t k ,
20
10
bl
- jM -• • i 1 i . . . L . . . .
20 25 20 25
0.6
0.5
0A
0.3
0.2
0.1
n
|—1—i—r
-
\v
—>—i—i—i—i—i—>-
s: ^---
28 30
13 15 17 19 21 23 25 27
"Mg Brems 83RyS
-(Y.po+Pil 8=90"di)
—(Y.Pol 6=90° 68DC105dfl
(mb)
ON
O
>2
mm
CO
O
( M O V )
Mg isotopes Brems 74VaS
al2*Mg o(y,xpl 64Is13
bl26Mg o(Y,xpl
do35
(pb/srl
300
200
100
ny
eoo
600
400
200
ft I
-
I
1 4
1 1 1 f L.
••
1' 1'IVH '••I V L*\ /
T . I , i*—r
' ^
• • . • • • •
T- , 1 i
al '
-
1
j j i -•
bl
•
-
1 * 1
Brems 83Ry5
16 20 24
EY (MeVl
b l • — ( Y , O Odn
Cmb")
17
24
16
V
0
IB
11 in "i in"1 in1'11'1''| j I j l " Ji * j f j i» '
( r ! - l 1 ' . . . . . '(r:'p) .
• bl/ l l l l -
1 .
1;
(mbl
14 18 22
EY (MeV)
a) ^ r , odn
=90dn
6=90
6=90 75KuI
25Mg Mono 75Be6 , 71A11
bl o(Y,nl + o(Y,pnl
cl o(Y,2nl+o(Y,p2nl
3
OSON
664 FORKMAN and PETERSSON
£ 5
"-£•*•
Mono 75Be6 , 71FU1
bl oCY.ni+oCY.pni
cl o(Y,2nHo(Y,p2nl10
Mg
GNGPG2NGNPG2PGA
U
A =
16.511.729.721.120.59.3
24
11S•\
2Ss
IB
EY
22
(MeV)
(78.99)
.33s,
.8573,
.6O2y,
8*
B*6*. EC
A =
7.312.123.919.022.6
9.9
26
25
S15.11.S
37.S
(10.
030h33s,
6s,
00)
, B"
B"
A =
11.111.118.423.224.810.6
26
S60sS
15.3.S
(11.01)
i 8
030h, 8"38 mln, 8
so
as
Aluminium
17 I9>20 23
(MeV)
2 7 M Mono 74VeS
o(Y,2n)+a(Y,p2n)
29
7A1 Mono 75Be6 , 66Fu1 2
a) o(Y,n t)
bl o C . .p
c) o(Y,2n)to(Y,p2n) v i • i • -i . H . i
12 „•., 16 20 24 L, 26 32 36
O
G0sCL
tn73<siVI
O
EY (MeVI
2TA1 Brems 81Is14
0.3
0.2
0.1
0
0.60.1
0.2
0
0.15
0.10
(mb/srl 0.05
0
0.2
0.1
do
(Y,pdn
Transitions to different levels in 26Mg
al 0 MeV bl 1.8 MeV cl 3.0 MeV
d) 4.4 MeV e) 6.6 MeV f) 8.5 MeV
gl 11.0 MeV M 13.0 HeV
00.08
0.04
010
cl
e)
20 25
(MeV)
Al A = 27 (100)
GN 13.1 7.l6E+5y, 8 \ EC6 . 3 6 s , B*
GP 8 . 3 SG2M 2H.M 7 . 1 7 1 s , B*CNP 1 9 . 1 SG2P 2 2 . 1 6 0 s , B"GA 1 0 . 1 S
27Al Brems SIRyS
al -°(Y,p..ldn
b) ^ ( Y , P , 1
dn
cl MT.PI Idf)
dl ^ ( Y . P i ldn
el ^-a(Y,poldn
e=90
8=90°
6=90°
e=90°
e=90°
5
OS1
668 FORKMAN and PETERSSON
o
ICO
ou
S ss
-i
15 20 ?5
EY (MeV)30
c) s oSi Mono 83Py1
82Od5
?0 23 26
EY (Me\O
29
•c
I
2 " S i Mono 74VeS
O(Y >n1 + o(Y ,pn) energy resolution
E=18O keV.
o(y ,nl + o(Y ,pnl energy resolution
E=350 keV.
0
(mb>
(mb)
abs x-170
20 2
EY (Me\O
2"Si tagged photons 83Gu1; 75AhS
O(Y ,tot)
30Si Brems 82Od5
o(y ,xn) no correction has been made
for double counting from the
o(Y,2nl reaction
Cmbl
--4
o
21 23(Me\O
2"Si annihilation Y 83Be47
O(Y,PO)
•nO73
2
Z
Sa•omm
VI
O
10 11 12 13 H 15 16
E Y (MeV)
'"Si Brems 82Od5
O(Y ,nl
SI A * 28 (92.23) A = 29 ("4.67) A = 30 (3.10)
GN 17.2 1.11s, B*CP 11.6 SG2N 30.5 2.21s, B*GNP 21.6 7.16E+5Y, B \ EC* 20.1 SG2P 19.9 S 21.9 9-16 min, 8~GA 10.0 S 11.1 S
8.5 S12.3 2.2t nin. 0"25.7 t.113, B*
10.6 S13.5 6.56 mln, B"19.1 S22.9 2.21 nin, B"21.0 20.93h, B"10.6 S
Phosphorus
15
0
(mb)10
5
0
J /.. J* /20
Ey (MeVl26
" P Mono 74Ve5
• o(Y,nl+o(Y,pn)O o(Y,pn1A o(Y,2n)+o(Y,p2nl
A= 31 (100.0)
CN 12.3 2 . 5 0 m i n , B*, ECCP 7 . 3 SG2N 23.6 1.15s, 8*CNP 17.9 SG2P 20.8 6.56 m l n , 8"CA 9.7 S
12 11, 16 18 20 22
E Y (MeVO
" P 74De4
a) o(Y,xnl Brems 69Is22
b) 0(Y,xn) Mono 73Be42c) O(Y ,xnl Brems
"0
5
Sulphur
(mb)
121 -IY.nl
"*S Brems
o(Y,nl + o(1
16
84As5
r,2nl+
EY
O(Y
20
(MeV)
,pnl
28
" S Mono 74Ve5
oCY,nl+o(Y,pn)
O o(Y,pnl
• o(Y,2nl+o(Y,p2n1
J"S Brems 84As5
16 20~IY-2nl 24
EY (HeV)
28
itO
Sa
3rojoC/JCO
O
A = 32 (95.02) A = 33 (0.75) A - 31 (M.21) A = 36 (0.02)
GNGPG2NGNPG2PGA
15.08.9
28.121.216.26.9
2S12SS
.61s
.22s
.197
, 0*
, 8 'mln, 8*,
8.69.6
23.7EC 17.5
18.27.1
S112S2S
.282d,
.61s,
.62h,
8"8'
8"
11.110.920.121.020.17.9
S25S
116S
• 30d,
.282d
.50£*
8"
, 6"2y, 8"
9.913.016.921.525.09.0
87.Id,17.5s,S
12.1s,2.8s,6.5OE+
B"8"
B"8"2y, 8"
Chlorine 20 •
10 •
Mono 74VeS
a) Cl naturalb) " C l
' "lY.-^aiY.l'M; ( m b )
' o(Y,2nl+o(Y,p2nl ' 0
10 - 99
Cl A = 35 (75.77) A = 37 (21.23)
GN
GPG2NGNPC2PGA
12.6
6.121.217.817.37.0
1.53s,32.0 mlnS2.51s,S
25.3Od,S
0*- e\8*
6"
10.3IT
8.118.918.321.17.8
3.OOE
SS
87 . Id ,17.1s,25.30d
+5y, B
0"B"
EC, 8*
ON
Argon
(mb) 20
20o
(mb, ^
012
" 8
(mblt
o
(mbl
J
; vdl
30
(mbl20
ONo
"°Ar Mono 74Ve5
Ar
GNGPG2NGNPG2PGA
A =
15.38.5
28.021.211.96.6
A
36
1.S0.1.SS
> o(Y,2nl+o(Y,p2nl
(0.
77s,
8>(s,53s,
3«>
B*
B*B*
A =
11.810.220.620.618.67.2
38
35SS3SS
(0.
,02d
.OOE
06)
, EC
+5y, B", EC, B*
>
a
v>{SI
O2
""Ar Brems 83Su5
al (Y,n)b) (Y,2n)O (Y,P!d) (Y.dJ+CY.nple) (Y.T)
Ar A = 1(0 (99.60)
GN 9 . 9 2 .69E+2y , B"GP 12 .5 5 6 . 2 mln, 8"G2N 16 .5 SGNP 20 .6 37.29 mln, B"G2P 22 .8 1.696E+2 mln, B"GA 6 .8 S
EY (MeVl
Potassium
"K Mono 74Vc5
• o(Y,2nl+o(Y,p2n)
O o(Y,pn)
(mb)
17 K. 2 0 2 3 «» 26 29
JO
A = 39 (93.26) A = 1)0 (0.01) A = f i (6.73)
GN 13.1 7.61 min. B* 7.8 S
GPC2NGNPC2P
6.1)25.218.216.6
0S1
35S
.93s,
.233,
.02d,
B
B*EC
GA 7.2 S
7.6 2.69E+2y, 8'20.9 7.61 min, B*1H.2 S18.3 37.29 n i n , B"6.1 3.00E*5y, B", EC, B 6.2 S
10.1 1.28E*9y, 0", EC, 8*
7.8 S17.9 S17.7 2.69E*2y, 8"20.3 56.2 min, 8"
Calcium
(mb)
:sH,
Mono 74Ve5
o(Y,n)+o(Y,pn)
110
90
70
50
30
10
0
(mb) 2 0
10
0
10
W t»o-i—5"10
50
20
10
0
i i i i
" /
15
r^o.U
i i i i i i |
a) --
f"\ ::/ \f \\_.
20 M 25-
, • • » * • ' •
/ \
c)
jf'iit f )
•
ON—JOS
15 20 25
Ey (MeV)
"Ca Drems 74Br1
a)-—o(Y,n t)+o(Y,p ) 68Be205
IIH64Ba5
O
>2:3a.i>PIHTOininO
(mb/srl
"2Ca Brems 81As5
al
bl (Y ,p l 75'J-hi 1
60
o "
(mb) 20
012 14 16 18 20 22 21! 26
EY ( M C \ 0
""Ca Brems 77OiS
a) o(Y,n)
Ca A = HO (96.91) A = H2 (0.65) A = M3 (O.1H) A =
b)
cl
d)
e)
fl
(90°)
do
a
0.8
0.6
0.4(mb/srl
0.2
0
al
20
69Wu13
2622 24
H Y (MeV)eCa Brems 78Th41
al (Y,pl (90 1 E >28 MeV
bl (Y,PO) (90°)
t
(2.09) Ca A = 16 (0.001) A = 18 (0.19)
CNGPG2NGNP
G2PGA
15.68.3
29.021.1
11.77.0
O.863,S0.139s,
8*
8*7.61 mln. 8*0.93a,SS
B*
11.510.319.820.1
18.16.2
1SS1
S
s
.03E
.28E
•5y, EC
+9y, 8", EC, 8*
7.910.719.118.2
19.97.6
S12.36h,1.03E+S
1.83h,2.69E+
B"5y, EC
B"2y, B"
11.112.219.121.8
21.68.8
S22S12
32S
.2h,
.36h,
• 9y,
8"
8"
8"
CNGPC2NGNPG2PGA
10.113.817.822.7•11.1
120S221132
.651E*2d, 8mln, 8
.2 mln, 8"
.87 mln, B"•9y, 8"
9-915.817.221.229.111.1
1.51d17.5s,S1.15EN
11.87
, B8"
+23, B~
mln, 8"
Scandium
(mb)
11 K 17 20 23 26
Ey (MeV)
(Mb)
O
>2
a•vmmonenO
"'Sc Mono 74Ve5 " S c Brems 82Ry1
O
A
o(Y,nt)
do
dn
(mb/sr)
Sc
CN
GPC2NGNPC2PGA
A =
11.3
6.921.018.019.)7.9
U5 (100)
3.93h, B*.2.lid, IT,S3.88H, 8\S22.2h, B"S
ECEC
EC
"5Sc Brems 77Oi5
a) (Y,P) C90")
W ( Y , P 0 H 9 0 ° " I do
dn(ub/si)
1.5
1.0
0.5
a • ••0- • — ! - - • .
b e-so*
k12 14 16 IB 20 22 24 26
EY (MeV)
t
J
Titanium
•"Ti Brcms 79Py5
a) (y,n)
b) (r .p) 8=90° E >2.7 MoV
O (Y,PO+PX) 8=90°
d) (Y.OO) 6=90°
o
(mb)
dodfl
dodn
dodn
(pb/srl
30
20
3.0
2.0
(mb/sr) t.O
OA
(mb/sr) o.2
80
°2
ON00O
'•'mi
bl
• • - • • +
cl
37i71
3ammc/i[/iO
iji rh rfi r-r-r-r-i20 22 2418 20
EY (MeV)26
C..0 -
18.0 -
(nb) »••
16.0 •
0.0
2.8
do 2 '
* 1.5
0.5
0.0
•
I 11
A$
/
KiV
a)
% '
Ibl
1 , *
11 V. 17 20 23 26 29E Y ( M C V )
"'Ti Brems 80SuS
a) (Y,n)
10 12 16 18 20 22 24 26EY (MeV)
5 0 Ti Brems 79!>y5
a) o(Y,n)+o(Y,2n)
b) O(Y,P)
f
b) 6=90°
T i A = 16 ( 8 . 1 ) A = 17 ( 7 . 1 ) A = W ( 7 3 . 8 ) A = H9 (5.M)
CN 13.2 3 .08h , B \ ECCP 10.3 S
C2N 22.7 18 .2y , ECCNP 21.7 3 -93h , B*. EC
2. l ) l )d, I T , ECC2P 17.2 SCA 8.0 S
8.9 S10.5 83.8Od, 6"
18.7s, IT22.1 3.08h, B*19.2 S
EC
18.79.0
1.651E+2d, B"S
11.6 SU.I 3.4?d, 6"
20.5 S22.1 83.80d, B'
18.73, IT19.9 S9.1 S
8.1 S11.ll 43.67/1,
19.819.6
S3.12d,
20.8 1.51d, 0"10.2 1.651E+2d, B"
Ti
GNCPG2NGNPG2PGA
A =
10.912.219.122.321.810.7
50
S57.
S13.
SS
(5.3)
0 mln, B~
67h, B"
Vanadium
00
to
80
0 60(mh)
M>
20
0
80
(mb) ,- ,i
a)
,2N)
b)
'l1
" ' I I I"'III
-
--
' H l i i l l l i
(mb)
51 V Mono 74VeS
Ey (MeV)
26
O
Zws
tnJOenCO
OZ
A o(Y,2n)+o(Y,p2n)^ o(Y,2n)+o(Y,pn)
10 12 V. 16 18 20 22 2<, 26
Ey (MeV)
" V Mono 75Be6 , 62Fu1
a) a ( Y , n t )
b) o(Y,n)+o(Y,pn)
c) a(Y,2nUo(Y,p2n)
V
GNGPG2NGNPG2PGA
A =
9.37.9
20.916.119.39.9
50 (0.25)
3.27E+2d,S15.98d, ECSM3.67H, B"83.8Od, B"18.7s, IT
EC
, B*
A =
11.18.120.M19.020.210.3
51
H
s3S573
(99.75)
.27E+2d, EC
.0 mln, 0"
.M2d, 8"
"0pa
00
684 FORKMAN and PETERSSON
"6o
•i
dfl
(mb/srl
0.3
0.2
o.t
0.013 17 21 25
EY (MeVl
HCr Brems 79Ts5
I — (Y.p.+pil (90°)
— - o(Y>nl 77Sht2
o(Y,p1 75TO35
Cr
GNGPG2HGNPC2PGA
A =
13.09.6
23.621.116.38.6
50 (D.35)
1)1.9 n l n , B*, EC3.27E+2d, EC
21.56h, EC15.976d, EC, 6'SS
A =
12.010.521.121.618.69.1
52
27.SS»Ss
(83.
701d
79)
, EC
A =
7.911.120.018.120.1
9.1
53
S3.
27.S5.S
(9.50)
716 n l n , B"701d, EC
80 min, B~
A =
9.712.117.720.922.0
7.9
51 (2.36)
S1..60 mln, B*S
3.1.S
.716 mln, 8"7 rain, 8" 5
00
Manganese
0
(mb)
0
(mb)
80
60
40
20
60
60
40
20
0
/A,,J ^
Xf\ . (».»•)' '(Mil) _
V :......
II
"V1 I1 (r,3
1 ' 1 • 1 • 1 •
a)
-
-
i1 ii U | i l -
. ' ' ' • ' • I . . .
b)
"! .110 14 16 22 26 30 34
Ey (MeVl
OS00O\
(mbl
(MeVl
Mn A = 55 (100)"Mn Mono 79A11
al
b)c)
el)
O(Y
O(Y
O(Y
O(Y
n 1
>n)+o(Y,pn),2n)+o(Y,p2n)
,3n)
GNGPG2NGNPC2PGA
10.28.1
19.217.820.1
7.9
3S3S1S
. l21E+2d
.7l4E*6y,
.60 mln,
, EC
EC
8"
O73
S
a•V
mm9VI
O
Iron
50
o
Cmb)30
13 15 17 19 21 ?3
5"Fe Brems 78No12
60 -
(mb)
(,0 -
20 -
-
i
_i
/AAi
\
\
\
\
17 19 21
Ey (MeV)
23
'T-e Brems 78No12
| °(Y,p) experimentO(Y,P1 calculated with isospin effectsO(Y,P^ calculated without isospin effects
Hf
Fe
GN
GPC2NGNP
G2PCA
A -
13.1
8.924.120.9
15.148.4
5M (5 .8 )
8.51 mln, B \ EC2.53 rain, IT3.7ME*6y, EC8.275h, B*. EC5.591d, EC. B*
21.1 mln, B , EC, ITSS
A =
11.2
10.220.520.1
18.37.6
56
2.
SS3.
SS
(91
68y,
122E
.8)
EC
+2d, EC
A =
7.6
10.618.817.8
19.67.3
57 (2 .
S
2,2.S
3.s
.58h,•68y,
1)
8"EC
.52 mln, B"
A =
10.0
11.917.720.6
21.57.6
58 (O.3)
S
1S2,
5,S
.51 mln, 6'
,58h, 8"
.91 mln, B"
688 FORKMAN and PETERSSON
4reo
O D O D
(II*)'
35
30
25
,20 h
15
10
5
0
Co
GN
GPG2NCNPG2PGA
A =
10.5
7.119.017.U19.37.0
59 (100)
7O.78d, EC,9.2h, ITS2.717E*2d,S1.51 mln,S
EC
B"
8
60
(mb)*
0
c)
: / ' % , ' ' , illl' " ' " ' " • ' " ' ^ T < " 1 1 ' ' "
d)
ib linn i1i i i i i i i i i i i i i
-
- >90
10 12 I t 16 1B 20 22 24 26 28 30 32 34 36
690 FORKMAN and PETERSSON
•i
-a;u
m CMm e * . —
•i
•Hi * « , 7SB* , 74R.1 " H i Mono 75W . 74B.1
a) o(Y,n )
c) o(Y,2n)+o(Nl
GNGPG2NGNPG2PGA
A =
12.28.222.519.611.26.D
58
362678SS
(68.
.Oh,
. lOd,
.76d,
27)
EC,
ECEC,
B*EC
B*
Nl
GNGP
G2NGNP
G2PGA
A =
11.49.5
20.1)20.0
16.96.3
60
7S
S709SS
(26
.5E*
.78d
.2h,
.10)
iy, EC, B
, EC, B*IT
A =
* 7.89.9
19.2MA
18.16.5
61
S5107S
44S
(1.13)
•27y, B".5 nln, IT,-5E+I4y, EC,
.56d, B"
B'B*
A =
10.611.1
18.1)20.5
19.97.0
62 (3.59)
S1.65h, B~
S5.27y, B"10.5 min, IT, B3E+5y, B"S
A =
9.712.5
16.520.9
122.78.1
61) (0.9D
1.001E+2y, B~27.5s, B
S1.50 min, B13.9 mln, B'68s, 0"3E*5y, B
70
Copper
a
(mbl
a
(mbl
a
(mbl
60
60
40
20
80
60
40
20
252015
105
- yV.«J
1
a)
' " • ' "
bl
/ \ . | . "
'"iMiiiii,!';
c)-
1 Illllll ll
. l '1 '1 1 ll,lrV.»)
1 . . .
10 12 11 16 18 20 22 24 26
Er CMeVO
80
60o
(mbl w
20
0
25 -
20 "0 15
(mbl ,0
5
I I T
'IMI
-
t • i •
a)
bl
OS
o
10 12 14 16 18 20 22 24
EY (Me\0
" C u Mono 7SBe6 , 68Su1
al oCy.ni
W o(Y,2n)+c(Y,p2n)
tlono 79nz14
o(Y,nl 68Su1
oCy.nl 64Fu1
lO
ns
3a"ammfoeninO
12 16 20 24
EY (Me\0
Cu Mono 75Be6 , 64Fu1
al o(Y,n tl
b) oCY.nl + oCY.pnl
c) 0(Y,2n)+<J(Y,p2n)
(mb)
(mbl
80
60
40
20
80
60
40
20
"v.«i
I'1!1' '^ < a . T —
al
r ^ %
A " :/ \
12 16 20
EY (MeVI
(mbl
40
30
20
10
0
-
IJ,) 12 16 20
EY (MeVI
cl
id i •T' l i . i r
6 ! t u Mono 7SBe6 , 64Ri1
a) o(Y,n t l
bl o(
c l o
(mb)
(mb)
(mb)
U I.,...,
• / \
I1
il'lii,11'
'""X,,
'"mill.
Hl'l11!!!!
al
bl
lull• i i 1
cl
' ' i l l -
8 12 16 20 2t 28
Ey (Me\T)
Cu natural Mono 75Be6 , 64Pu1
Cu A = 63 (69 .17 )
65Cu Brcms 81Sh45
a) OCY ,n)
b) o(Y,p)cl O(Y ,a)
Solid line: calculated
cross-section assuming
isospin splitting (T<(T )
given by Falliero's
formula 71Pa8.
A = 65 (30.83)
CNGPG2NGNPC2PGA
10.96.1
19.716.717.25.8
9S3S1S
.73 min,
• th , B\
.65h, 8"
8 ,
EC
EC 9.97.1
17.817.120.0
6.8
12SS1
.70h,
• 001E-I27.5s, I
1.65h,
EC,
• 2 y ,
3"8"
B ,
8"
B
lOJO
s•zto3a."V
m
enO
a) o(Y,ntl
b) o(
c) o(Y,2n)+o(Y,p2n)
PART 4-1 695
See overleaffor the graphs of zinc
Zinc
6*Zn Brems 70Co8
200 —
160
(Y,n)
(Y,n) + (Y
(Y.pn)
- - (Y,2n)
,pn) + (Y, 2n)
a(mb)
120
80
40
20
T I I I I I I I I I I I I I I I I I
0 I i i i I / I i i i i i i i i i i i i i
8 10 12 V, 16 18 20 22 24 26
E Y (MeVO
60
30
20 25
Ey (MeV)
30 35
12 V, 16 18 20 22 24
HY (MeV)
as
o
S
z3a."ommtoenc/)OZ
•*Zn Brems 73C15Breras 68OwS
(V.P)- - - 6Jai(Y,n)"Qi
6"Zn(Y,n)6SZnZn
CNGPG2NGNPG2PGA
A :
11.97.7
21.018.613.81.0
61
38.S9.9.SS
(18.6)
0 min,
13h, EC73 mln,
8\
. BB*
EC
, EC
Zn A = 66 (27.9) A = 67 (1.1) A = 68 (18.8) A = 70 (0.6)
CM 11.1 2.l|M0Et2d, EC, B* 7.1 S 10.2 S 9.2 55.6 min, 8 ' >11.Oh, IT, §" 2
CP 8.9 S 8.9 5.10 min, 0" 10.0 62.01h, B" 10.9 3.0 rain, 8' H
G2N 19.0 S 18.1 2.11tOE+2d, EC, B* 17.3 S 15.7 S TGHP 18.8 12.7Oh, EC, B \ B" 16.0 S 19.1 5.10 min, B' 19.5 30s, B' **
3.8 rain, IT, B"G2P 16.1 S 17.3 2.5h, B" 18.5 51.8h, B" « «GA I).6 S 1.8 1.001E+2y, B" 5.3 S 6.0 51.8h, 8"
Germanium
40
70Ce Brems 75Mc1
a) O(Y,I»)
b) o(Y,2n)+o(Y,p2n)
c) o(Y,n)+o(Y,2n)+o(Y,pn)+o(Y,p)
(mb)
150
100
50
0
30
20
W
0
150
100
50
0
1 I I
" a)
. • ^ ? _ _
~ b)
-
— • -
-
_ c)
j
i'V.fi,
1 1 1 1 1 1 1 1 1 1 1 1 1 -
-
I \ >j*H{ -
20 30
By (MeV)
1,0
72Ge Brems 75Mc1
a) o(Y,n)
c) a(Y,n)+o(Y,2n)+o(Y,pn)*o(Y,p)
o7)7*.
v3D.•0mHw73in(AOZ
o
150
100
SO
0
40
20
0
150
100
50
0
—i r~
- a)
-J
• b)
- c)
- /
~'\f- f ,
A
i . i . c i
Af \r r
JuxL-'r:"..1"5
1 1 i i
I ! i i
jy I T
• 1 1 1
1 1 • •
-
, i-
:
-
-
\ ^ -
(mb)
150
100
50
0
20
0
150
100
50
0
_ | I
a)-
- /
yi.
-
- /
1 1
/ •f
r.»p>
/
i i
r
1 1 1 1
V... 1 1 <
X*— ' L A
< 1 • <
.!'•"'. 'V
-
• —
1 1 1 1 1 I 1 1
I 1 1 . . 1 • 1
1 ' 1 1
20 30
EY (MeV)
10 20 30 40EY (MeV)
"8
5
7*Ge Brems 75Mcl 76Ce Brems 7SMc1
a) a(Y,n)b) o(Y(2n)+o(Y,p2n1
c) o(Y,n)+o(Y,2n)+o(Y,pn)+o(Y,p)
a) o(Y,n)b) o(Y,2n)+o(Y,p2n)
c) o(Y,n)+o(Y,2n)+o(Y,pn)+o(Y,p)
oo
9 11 19 24 29 34 39
EY (MeV)
6
4
2
0
o 6
Orb) 4
a)
- c)
O50
>
Sa
37)caenO
12 17 22 27 32 37 42
EY (MeV)
'"Ge Brems 73Mc5 Ge isotopes Brems 73Mc5
a) 70Ge(Y,pn)"Ga
b) "Ge(Y,pn)7'Gac) 76Ce(Y,pn)7*Ga
Ge A = 70 (20.5) A = 72 (27.1) A = 73 (7 .8) A = 71 (36.5)
GNGPG2NGNPG2P
GA
11.8.
19.18.15.
1.
55781
1
39.S2.
68.S
S
05h, EC
88Et2d,33 rain,
. B'
ECB\ EC
109
181917
5
.7
.7
.2
.0
.6
.0
11.SS
2 1 .S
S
15d, EC
10 mln, B~, EC
6.810.017.516.518.5
5.3
S11.12h, B"11.15d, ECS2.15'mln, B'3.9h, B~
55.6 mln, B"11h, IT, B"
10.211.017.020.219.9
6.3
Si .s
11.46.
S
86h,
12h,
B"
B"8"
Ge
GN
GPG2HGNPG2PGA
A =
9.1
12.015.920.622.1
7.5
76 (7
82.7818s,2.10S8.25
95s,16.5h
.8)
mln,6"min,
mln,B', B"
B"
B"
B"
3
Arsenic
5As Mono 75Be6 ,69Be101
a) o(Y,nt)
b) o(Y,n)+
c) o(
100
75
(ral)l50 -
125
100
75
° 50
0 * 1 25
0
A3
CNCPG2NCNPC2PGA
A =
10.26.9
18.217.117.95.3
75
17S
80S1|S
(100)
.79d,
• 3Od,
.86h,
EC, B*. B"
EC
B"
o(mb)
40
30
20
10
0
-
-
fr,n>•
-
-
- i.*
'(r.»)
-
-
1,,,
1
/
1
I
i
1
\
'(y,2ii)
• • • ,
ii
iin<
1 '
1
I
i
i j l
L
" .
I
•
,
' i l l
1
1
\
1
i
„
'I
—,—ral
ll,l'
''ll11
-
-
-
-
-
11
1 1
o
11O
"am
OZ
19 12 H 16 18 20 22 24 26 28EY OtoV)
Selenium
Se
GN
CPC2NCNPG2PGA
A =
12.)
8.520.719.311.21.1
71 (0.
7.i8h11 mln8O.3Od8.10d
26.Oh,SS
9)
, 8*, IT, EC, EC
e\
, EC, B \ EC
EC
A =
11.2
9.519.219.816.15.1
76
1.
S
s17.SS
(9 .0 )
185E+2d,
79d, EC,
EC
B\ B"
12 14 16 18
Ey (MeV)
20 22
Se Brems 67Co7
o(Y,Tn)
•V
I
Se A = 77 (7 .6) A = 78 (23.5) A = 80 (19.6) A = 82 (9 .1 )
GN 7.1 S 10.5 S; 17.1s, IT
GP 9.6 26.32h, B" 10.1 38.83h, B"G2N 18.6 1.i85E+2d, EC 17.9 SCNP 16.9 S 20.1 26.32h, B"C2P 17.3 82.78 nln, B" 18.1 S
18s, IT, B"GA 5.7 S 6.0 S
9.9 46.5E*1y, 8"3.90 mln, IT
11.3 9.01 mln, 8"16.9 S20.1 90.7 min, B"20.6 1.17h, B"
7.0 S
9.3 18.2 n ln , B"57.3 nln, IT, 8"
12.2 33s, B"16.0 S20.2 15.2s, B"22.7 29.5s, B"
8.2 1.17h, B"
O
Rubidium
Rb natural Mono 75Be6
a) o(y,n t)
b) o(Y,n)to(Y,pn)
c) o(y,2n)+o(Y,p2n)
(nJO
Rb
GN
CPG2NCNP
G2PGA
A =
10.5
7.019. H17.5
17.76.6
85 (72.17)
32.77d, EC, 8*,20.5 min, ITS
86.2d, ECS; 1.83h, IT
2.39h, B"S
B"
A =
9.9
8.618.618.5
20.58.0
87 (27.
18.82(1,
.83)
, B"1.02 min,SS
10.7y, B"
2.87 mln,2.39h, B'
, ECIT
, ITB"
50
200
150
0 100(nib)
30 -
71Le5 ( n l b ) 20
10
0
• 1 • I •••• 1 -
-
1 1 1
\ I
[ 1
1
IM.1
b)
i i i i i
to 12 14 16 18 20 22 2*.
Ey (MeV)
73
Strontium o
200
150
(mb)100 -
50
0
200
150a
(mb) 100
50
0
40
30a
(mb) 20
10
0
1 • 1
1 1
1 1
1
Mr..)
-
-
-
i i
" I ' I
/
/
/
i i
\
MT,2
y
>.
•(r.2
JI i
V
•)
1 1
a)
b)
c)
12 K 16 18 20 22 2« 26
HY CMOV)
8 9Sr Brems 79Sh10
o O(Y,P) from (e.e 'p) data
X o(r,p) 76Br1
• o(Y>n) 71LeS , 74Be5
. O(Y,PO) 74ShS
•••• Lorentz l ine
Im
c/iO
10 12 H 16 18 20 22 21. 26
F.Y (MuV)
Sr natural Mono 75Be6 , 71Le5
a) o(Y,nt)
b) o(Y,n)+a(y,pn)
c) o(Y,2nUo(Y,p2n)
Sr A = 84 (0.5) A = 86 (9.9) A = 87 (7.0) A = 88 (82.6)
GN 12.0 32.th, EC, B* 11.5 6U.85d, EC 8.1 S 11.1 S; 2.80h, IT, EC5.0s, IT 68 mtn, IT, EC
GP 9.0 86.2d, EC 9.6 S g.t 18.82d, B", EC 10.6 l).72E+1Oy, 0"1.02 min, IT
C2N 21.2 25.Od, EC 20.0 S 19.9 6"J.85d, EC 19.5 S68.0 min, IT, EC
GNP 19.8 1.25 min, $*, EC 20.1 32.77d, EC, 8*, B" 18.1 S 20.5 18.82d, B~, EC6.2h, EC, B* 20.5 min, IT 1.02 min, IT
G2P 11.6 S 16.7 S 18.0 10.70y, B" 19.2 S1.48h, B", IT
GA 5.2 S 6.3 S 7.3 S 7.9 S
Yttrium250
2000
150(mb)
100
50
0
250
200
(Ib)15°100
50
0
40
30o
(mb) 20
10
A- / ',-_-
a)
b)
-
c)
-Jo00
O
2
2
mm90enVIO2
10 12 14 16 18 20 22 24 26 28
EY (MeV)
10 12 11 16 18 20 22 24 26
Ey (MeVI
89Y Mono 75Be6 , 71Le5
a) o(Y,nt)b) o(Y,nl+o(Y,pn)
c) o(Y,2n)+o(Y,p2n)
'Y Mono 75Be6 , 67Be1
a) °(Y,n t)b) o(Y,n)+o(y,pn)c) o(Y,2n)+o(Y.p2n)
V
GNCPG2N
GNPG2PGA
A =89 (100)
11.57.1
20.8
18.217.78.0
1.066iE+2dS
80.3h, EC,13h, IT, B*S; 2.80h,1.72E+10y,S
• EC, 8'
B*, ECIT, ECB~
(nib)
10 11 12 13 K 15 16 17 18 19
Ry (MeV)
" Y Mono 75Be6 , 72Yo7)
(ub)
12 H 16 18 20 22 24
Ey (MeV)
Brems 80Va1
a) • " Y o(Y,Po)
" S r o ( p , ' ) 73Pa42
b) O(Y,P ) from o(e,e 'p) data 74Sh5o
40
30
o
(lib) 20
1.0
0.5
00.50.5
0
0.5
1.0
1.5
"1• I I I
11.c)
•
1
ll
' i l l 1 l» i ' l l|
1,"
1
1 ( l,i«r •
• i i
Vii
-
S.,|'
II11!1 •
_ j-
l i l l l :1
V. 16 18 70 22 2<i
EY (HeV)
8SY Brems 80Va1
a) O C Y . P ^
W a '
c) a 2
o7)
3Q."0
m7)VICO
O
PART 4-1 711
See overleaffor the graphs of zirconium
Zirconium
3
a
(mb)
o
(mb)
160
120
80
40
0
160
120
80
M
0
— i - I - • • i —
1I
1
-
*
.*
\ \V
\\\,""/m
•HI
a)
-
JusHi^hiii
b)
-
-
l''ll illiiiM
a
(mb)
o
(mb)
200
150
100
50
0
200
150
100
50
0
Mr..)
-' V ' i
*
- M\
a)
''"v.
b)
-
!2
2
Itn7>VIV)O
a
(mb)
40
30
20
10
0
-
-
-
10 12 14 16 18
EY
•i
20
(MeV)
0
-
22 24 26
0
(inb)
40
30
20
10
0
'"Zr Mono 7SBe6 , 67Be1
a) o(Y,nt)b) o(Y,n)+o(Y,pn)c) o(
10 12 14 16 18 20 22 24 26
EY (MeV)
90Zr Mono 75Be6 , 71LeS
a) o(Y,nt)
b) o(Y,n)to(Y,pn)c) o(Y,2n)+o(
5
10 12 14 16 18 20 22 21.
KY (MeV)
90Zr Brems 79Sh1O
o O(Y,P) from (e .e 'p) data
X O(Y,P) 76Br1
• ofy.n) 71Le5 , 74Be5
• O ( Y , P ) 74ShS0
•••• Lorentz l ine
200
150
a
(nib) 100
50
0
' ' ' ll ' ' '
1,\
- / \J '-I . I . I
1
-
-
•
0 10 20 30T;Y (MeV)
Zr natural Mono 82Ve4
3n
a.•vWHm»
o
Livermore 67Be1
6 8 10 12 U 16 18 20 22 24 26 28 30
HY ( M O V )
" Z r Mono 75Be6 , 67Be1
a) o(Yint)b) o(Y,n)+o(Y,pn)c) o(Y,2nl+o(Y,p2n1
175
150125
0 100
(mbi 75
50
25
0
175
150
125
o 100
(mb) 75
5025
0
80
60
0
(mb)
20
-
--
-
-
-
fa")
-
--
-
J V
,—i . i—.—i—, i—,—i . i—. i—.—i—.—• i • , —
J \•hi iHi|||i|,|l i|||l||
V.2D) ll'i " ' I 1 " "
c)
/ V1 Illllll
H
t
8 10 12 V. 16 18 20 22 24 26 28 30
EY (MeV)
" Z r Mono 75Be6 , 67Be1
a) o(Y,n t)
b) o(Y,n)+o(Y,pn)
c) a(Y,2n)*a(r,p2n)
716 FORKMAN and PETERSSON
Ti i )
O O ui
i i i I \
a L—
1 I I ! 1 1 1 * ' .
Fi-
„ £
_=- s i
%© «*• COS S o
Zr
GN
GPG2NGNPG2PGA
Zr
GNGP
G2N
GNP
G2PCA
A =
12.0
8.421.319.815.46.7
A =
7.28.7
19.2
15.6
16.35.5
90 (51.5)
78.4h, EC,4.18 min,S; 16.13,83.4d, EC1.066E+2d,SS
91 (11.2)
S64.1h, B"3.19h, IT,78.4h, EC,4.18 min,S; 16.1a,
50.55d, B"S; 2.80h,
B*IT, EC, B*IT
EC, B*
B"B'IT, EC, B*IT
IT, EC
A
89
15
17
173
=
.6
.4
.8
.3
.1
.0
92
S5849S
6'l328S
(17.1)
•5d, B".7 mtn, IT
. 1h, B"
. 19h, IT, B"
.82y, B"
A
810
14
17
183
=
.2
.3
.9
.8
.9
.8
a)
b)c)
d)
94
IT Mono
olY,
0(Y,
°(Y,o(Y,
(17.
1.53E*10
S
.25h,
3.54h,
2,28,
• 71h,• 82y,
n 1
Vn) +
75Be6 ,
o(Y,pn)
67Be1
,2n)+o(Y,p2n1
3n)
4)
6y,B"
B"
B"B'
A
0* 711
14
18
214
=
.8
.5
.3
.5
.3
.9
96
63.10.
S
18.
74.2.
(2.8)
98d, B"3 min, 0"
7 min, B"
13, B"71h, B"
70
Niobium
Nb A = 93 (tOO)
CM 8.8 3.2E+7y, EC1O.15d, EC, B*
GP 6.0 SC2M 16.7 \ EC
62d, IT, ECGNP 1M.7 SC2P 15.1 58.5d, B'
19.7 min, ITCA 1.9 S; 16.1s, IT
"Nb Mono 75Be6 , 71LeS
a) o(Y,nt)bl o(Y,nHo(Y,pn)c) o(Y,2n)+o(Y,p2nl
0
(mbl
0
(mbl
a
250
200
150
10050
0
250
200
150
100
50
0
75
50(mbl
25 "
0 - i
• 1 • 1
MM)
-
-
'(Ml
l i
1 •
J1
. /
HI.II)
•\V
/
•ll.lil
1 1 -
paH
10 12 V, 16 18 20 22 24
EY (MeVl
Molybdenum
150 "
a 100
(mblSO
0
150
o 100
(mb)50
o
(mb)
C D (»,Ji)
' I . L—. I I , I
" \
-i——i 1
cl
12 14 16 18 20 22 24 26 28
Hy (MeV)
(mbl
(mbl
100 -
I50
0
150
100
SO
0
60 -
a 1,0
(mbl20
• . ._ , r-
1"
, i
—. !
1
J1 .
"T—*~
t
/
i
J
/
1
1
'A
i
~—T"
— T -
illll
\
\
W.2.)
I 1
1
1
fr,»)
I . .
"—i—•—i—
"|lII1
1
1
•Hi'
, ,
1 '
' . 'l 1 •1 ' I."' , '
. 1 1
-—i—•—r-
ll.1 l|| |Vll| ,
al
-
• i
bl
•••*• ii HI ,
1
" " • " ' i r •
cl
I'NIII ll
10 12 14 16 18 20 22 24 26 28
E Y (MeV)
O
a
mtn90v>VIO
"Mo Mono 75Be6 , 74Be5
a)b)c)
9"Mo Mono 75Be6 , 74BeS
al o(Y,ntlb) o(Y,n)+o(Y,pn)
c) o(Y>2nl+o(Y,p2n')
14 16 18 ?0 2 2 " 24
E> ( M e V l
92Mo Mono 74BeS
71Sh11
5
722 FORKMAN and PETERSSON
- J -
- ,_ -€j s-
s
1J1
• . . . . % \
[ ' ' ' ' '
__-
S - r L i |
L ?[i -~-_
I 1 1 1 1 " ^
s
-
u —=T~,
_
s -
-
s
_
s -
I § § s s
J
:</
I t [ \
S
-
-
_ =
L ^
-
-
s -
-
, , , , r 1o o
15
10
5
i i
-
-
-
'ir.«l
1
I
• i • I •
i i
I
•
! 1
d)
1'"" fill
I'll1 1
rj 1 .II
i|
i
8 10 12 U 16 18 20 22 21 26 28
EY (MeV)"Mo Mono 75Be6 , 74Be5
a) o(Y,n t)b) o(Y,n)+o(Y,pn)c) o(Y,2n)+o(Y,p2n)
d) o(Y,3n)
(nib)
15
10o
(mb) 5
150
100
SO
n
*•
' • &
•
«..
r ,*
• * *
/
i
J . ,1 i • i
Tit;
'A
k\ IV*
1 1 1
1 1 • 1 •
-
-
1 . 1 " ' , .
1 1 1 .
10 12 K 16 18 20 22 24 26
li (MeV)
. ,—.—(—.-•1—.—r-— ! — ^ - . ,
-
l».«l V.MI
1 1 I 1 1 1
• 1 • 1 • 1
d)
ini,».w|l | | l1 1 1
III"
i
8 10 12 K 16 16 20 22 24 26 28
Hy (MeV)
"Mo Mono 75Be6 , 74Be5
a) o(Y,n t)b) o(Y,n)+a(Y,pn)c) o(Y,2n)+o(Y,p2n)d) o(Y,3n)
Mono
o
A
•
V
74BeS
9 2Mo
"•Mo
" M 3
O(Y.
o(Y,_cv
o(Y»1 0 °Mo O ( Y
nt)n 1VV
724 FORKMAN and PETERSSON
I
Ho
GN
CP
C2N
GNP
G2PGA
Mo
CNGP
G2NCNP
G2PGA
A =
12.7
7.5
22.8
19.5
12.65.6
A =
6.89.2
16.016.1
16.52.8
92 (11.81)
15.19 min, B*65s, B\ EC,\ EC
62d, IT, EC5.67h, EC, B
11.6h, B\ EC18.8s, ITS83.Id, EC
97 (9.55)
S23.35h, B"
S31.97d, B"87h, IT, 8'63.98d, B"1.53E+6y, B"
, ECIT
A
8.9.
15.17.
17.3.
68
59
33
A = 91
9.7 3.6.
8.5 S;
17.7 S
17.3 3.10.
11.5 S2.1 S
98 (21.
S72 min,
(9.25)
5E+3y,9h, IT,13.6y,
2E*7y,15d, EC
13)
B"1.0 min, B"S23.35h,
SS
B"
ECECIT
EC, I
A
8,10,
11.18,
19.3.
B*
.3
.6
,2.0
.5,2
A =
7.1
8.6
17.0
15.9
15.12.2
95 (15.92)
S
2.03E+1y,636S
1S
100 (9.63)
66152S2
5130S
.02h, I
.03, B
.6 min,
• 9s, Bmin, I• 7s, B
3"
3"
.26 min,•5E+3y,.9h, IT,; 13.6y,
• 53E*6y.,
B"
B"IT, B*
ECECIT
B"
A =
9.2
9.3
16.5
17.8
16.12.8
96 (16.68)
S
31.97d, B"87h, IT, B"S
2.03E+1y, B"
SS
"0
t o
Rhodium
200
0 150
(mb) 100
50
0
200
150
Onb l 1 0 0
50
Rh
GN
GPG2N
GNPG2PGA
A =
8.1
5.318.6
12.713.72.2
103 (100)
2.9y, EC2.06E+2d,S3.3y, ECH.31d, ECS
11.3 mln,2.1l4E+5y,6 . 0 2 , IT,
EC, B \
, IT
B"6"B"
8", IT1 0 3Rh Mono 75Be6 , 74Le5
a) o(Y,nt)b) o(Y,n)+o(Y,pn)
c) o(Y,2n)+o(Y,p2n')
80
600
( ki ^Imo)
20
0
-^—,—,—, ,—.—J—.—t
I1 (l
I1 1
\t,*\ b.ai
t
a)
i
b)
• c%
-
1 1 1 1 1
1 1 1 ,1
3
zo.mm73v>O2
10 12 14 16 18 20 22 24
Ey (Me\O
Palladium
Pd A = 102 ( 1 . 0 )(mbl
A = 10M (11.0)
GN 10.6 8.17h, EC, B* 10.0 I6.96d, ECCP 7.8 3.3y, EC 8.7 S; 56.1 min, IT
1 . 3 1 d , EC, ITG2N 18.9 3.63d, EC 17.6 SCNP 17.7 20.8h, EC, 6* 18.0 2.9y, EC
2.0bE+2d, EC, 0% 0", ITG2P 13.3 S 111.9 SGA 2.1 S 2.6 S
o
(mbl
Pd A = 105 ( 2 2 . 2 ) A = 106 ( 2 7 . 3 )
CN 7 .1 SGP 8 . 8 4 2 . 3 3 , 0", EC
1.31 mln , I T , 0"G2N 17.1 I 6 . 9 6 d , ECGNP 15.8 S; 56.1 rain, IT
C2P 15.7 39.35d, B"CA 2 . 9 S
9 . 6 S9 . 3 3 5 . t h , B"
15s, IT16.6 S18.3 12.3s, 8", EC
1.31 mln, IT , 0"16.1 S3.2 S
(nibl
Pd A • 108 (26.7) A * 110 ( 1 1 . 8 )
CN 9.2 6.5E*6y, B"2 1 . 3 s , IT
GP 10.0 21.7 mln, B"G2H 15.8 SGNP 18.5 29.8s, 8~
1.30E+2 rain, B"G2P 17.8 3.665E+2d, B"GA 3.9 S
8.8 13.13h, B~U.69 mln, IT
10.5 80s, B"15.0 S18.7 16.8s, 8"
6.0 mln, B"19.2 1.5 mln, 0"1.1 3.665E+2d, 0"
200
150
100
50
0
200
150
100
50
(J
60
60
to
20
U
1 r—
a)
I
1 i i
. b)
IT,II
1 I—'—• 1 ' 1—
- c )
-
' |T1'
1 1
1
I
I
f
—i r~
i. H
i i
1
•l
1
'i
" ,
<
"* 1 *~
11 ' . '
1
1
i
-
-
-
1
I ' • —
1"Illl-
1
16 18 20
Pd natural Mono 75Be6 , 74Le5
al o(Y,ntl
bl a(Y,n)+o(Y,pn)
cl a(Y,2nl+<i(Y,P2n1
5
728 FORKMAN and PETERSSON
• / — -
J D
l l 1 t I
< 1 1
u ~ -
1 1 t
»-"
1
O O O o O Oin ^ ui ^ LPCM CM *~ 2
- i 1 1 r
o>>
—r
1 I I
(mbl
7Ag Mono 75Be6 , 69Be10l
a) o(Y,n t)
b) o(Y,n)+o(y,pn)
200
100
ft
ai• - • • .
• .
10 12 U 16 18 20 22
EY (MeV)
1C7Ag Mono 74LeS
a) o(Y,nl+o(Y,pn)
b) o(Y,2n1+o(
Ag natural Mono 75Be6 , 74Le5
al a(y,ntl
b) o(Y,n)+o(Y,pnl
c) o(Y,2n1*a(
flg A = 107 (51.83) A = 109 (48.17)
9.6 21.0 mln, EC, 8*, (8~) 9.2 2.1 mln, EC,CN 9 ,8.5d, EC
CP 5.8 SG2H 17.5 f1.3d, EC, B*
7.2 min, IT, ECGNP 15.M S
G2P 15.1 35.Mh, B"15s, IT
GA 2.8 S; 56.1 min, IT
, , B1.27E+2y, EC, B*, IT
6.5 S16.5 S; 11.33, IT
15.7 6.5E*6y, B"21.3s, IT
16.1 21.7 min, B"
3.3 35.In, $'153, IT
70
O
Cadmium
Cd natural Mono 75Be6 , 74Le5
a) o(Y,nt)
b) o(Y,n)+o(Y,pn)c) o(Y,2n>*°(
200
150a
(mbl 100
50
0
200
150a
(mbl 100
50
0
80
a 6»
(mb) t 0
20
0
I I I "
-
' I T . . .
-
-
V..,1 1 1
.—1—•—I—•—1—•-
-
1 1 1
' I
'ir.jn
—i—•—i—-
, . , .
-i—•—i—*-
i
I . I .
i •
. . .
~ 1 . ,
al
b)
i . 1 ,
c)
.
wo
s>
zuao.mH
enO2
6 8 10 12 I t 16 18 20 22
RY (MeVl
Cd
CNGP
G2NGNP
G2P
GA
Cd
GN
GP
G2NGNP
G2P
GA
A =
10.97.3
19.317.2
12.3
1.6
A *
9.1
9.6
16.118.5
16.8
3.5
106 (1.3)
56.0 mln,11.3, EC,7.2 min,
57.7 min,69 min, 8'33 mln, 8'S
S
112 (21.1)
EC,B*IT,EC,
B*
ECB*
, EC, EC, IT
Sj 18.6 mln,
7.15d, B"65s, IT, BS21.1s, B",2.52E+2d,S
S
ECB",
IT
IT
A
10.8.
18.17.
13.
2.
A =
6.5
9.8
15.916.2
17.6
3.9
= 108 (0
3 6.5Oh1 S; 11
3 S
.9)
, EC, B*.3s, IT
7 21.0 mln, EC, 0*8.5d,
9 S
3 S
113 (12.
S
3.11h,
S; 18.67.15d,
65s, IT,22 mln,
EC
2)
B"
i min, IT
B'B"B'
5.5h, IT, B"13.<)3h, B"1.69 min, IT
A
9.8.
17.18.
15.
2.
A =
9.0
10.3
15.618.8
18.3
1.1
= 110 (12.5)
9 19 S
2 S1 21
1 S
9 S
111
9.11y5.1.S3.
21.
S
.53E+2d, EC; 39.8s, IT
.1 mln, B",
.27E+2y, EC
(28.7)
3E+15y, B", B". IT37h, B"15 min, B"
11h, 0"
12h, B"
EC,
A
8
11
1119
a
1
L B
Vt
--
.7
.1
.8
.1
.9
*IT
11
531120
A
7,9.
16.15.
16.
3.
6 (7
.In,
.8d,min
18s, BS1
2
21
.52s
=
.0
.1
99
2
3
111
s21.2.1.S;
13.1.6.21.
.5)
BS
.1 mln
. 12ht
-
B"
B"
, B'
8"
(12.8)
Is, 8\52E*2d,53E+2d,39.8s,
13h, B"69 mln,5E.6y,3s, IT
ECB", ITECIT
B"B'
9
Indium
220
180
a
(mbl.
100
60
/
1
1f
!
\
a) "
mnilll
lll
1
. . 1
o
(mb)
20
12 15 18 21 12 15 18 21
EY (MeVI '
a
(nib)
111In Hrems 83Go7
a) (Y,n)ll2Inm
bl (Y,nl112lng
cl (Y,nlll2ln
0
(mbl
12 15 18 21
Ey (MeVI
250
200
150
100
50
240
180
120
60
0
120
90
60
30
0
/ \
A,'i
1
i
'vliv.i. 1 !>.?•>1 I I I I1 i 1
1 1 1 1 1 1
-
-
ll'll"II
1I
I)
! i* i . i' ,'.i . i_
i
1
"•'ii.
a)
1
b)
Unlil'VUn,!' ¥•>, '1 1 1
C)
''"''ili'n |l 1
-
----
-
-
-
-
nlI,11
-
-
-
i
z
IIB
m73Ui
O
no
180a
, , , 120(mbl
60
0
240
160
(mbl m
60
0
60
600
(mbl w
20
0
-
- yf
-
-
—•—p—•—i—•—r
-
I...,
••"y a)
ir.nl
b)
'•.
i i I I . I
1—•—i r—— i——
c)
10 12 14 16 16 20 22 2*.
E Y (MeVl
1 1 5 I n Mono 7S15c6 , 74LeS
nl o(y,n )
b) oCy.ni+oCY^nl
cl o(Y,2nl+o(Y,p2n)
a
(mbl
In
32
24
16
a
0
-
i i i i1 i
• i • i • i
.11, ";3> ' i '
d
jl11
-
•
r/i
6 10 12 14 16 18 20 22 24 26 26 30Ey (MeVl
llsIn Mono 75Be6 , 69Fu1
al o(Y,ntl
bl o(Y,nl+o(Y,pnl
cl o(Y,2n)+o(Y,p2nl
dl o(Y,3nl
A = 113 (U.3) A = 115 (95.7)
9.1 11.1 min, EC, 8\ B" 9.0 71.93, B", EC,CN 9 , ,20.9 min, IT
GP 6.1 SC2N 17.1 2.83d, EC
7.6 min, ITCNP 15.5 S; 1)8.6 min, IT
G2P 15.7 7.H5d, B"65s, IT, B"
CA 3.0 S; 39.83, IT
, , ,M9.51d, IT, EC
6.8 S16.3 S; 99.5 min, IT
15.9 9.3E+15y, B"11y, B", IT
17.1 5.37h, B"1.15 min, B"
3.7 7.45d, B'65s, IT, B"
-0
7
Tin
200
100
0 o(nib)
0
•
al ,..'"' r•' -''\
;
; A..* \
• '' ' T~i 1 ' — I — —
'•
1 . ' • ' i t , _
oh-
0
012 16 20
RY (MeV)
2A
Sn isotopes Mono 74CaS
a) 12"Sn o(Y,ntlbl 120Sn o(Y,ntlcl l " S n o(Y,nt1dl ll'Sn o(Y>nt)el ll'Sn o(Y,ntl
(mbl
"I Ti—'—r—•—r
12 16 20 2". 28V.y (MeV)
Sn i s o t o p e s Mono 75Be15
a)b)
c)
il)
e)
f)
12 "Sn120Sn
"°Sn
""Sn11 'Snl l 6 Sn
O(Y
O(Y
O(Y
O(Y
O(Y
O(Y
,n t),n t)
.n t l
•V,n t l
. n J
O
sa.•0ro
tn
s2
240
180a
(mbl i2o
60
0
120
90a
(mb) 60
30
0
AI——r—-—r~—i—•—i—•—i
al
b)
• ' " ' l l ' l
HIU l i
240
1800
[mb)«0
60
0
120
90
0
Onb)60
30
0
. . . . , !
-
-
1
I1 1
-
-
ir.o)i
I
i
I
I '
i
i1'
I
• I •
I
'i
'ii
ti
1 •
r
i
i • • i • i •
al
\
iir in iH,,
i i , ' •
1 ' 1 • 1 '
bl
-
.1
10 12 U 16 18 20 22 24 26 28 30
1W (MeV)
8 10 12 U 16 18 20 22
Ey
lltSn Mono 75Be6 , 69Fu1
a) o(r,n)+o(Y,pn)b) oCT^ni+o
6Sn Mono 75Be6 , 74Le5
al
bl
(mb)
';" , , . .I'M" . l''MlllltTM*Ti
(mb) W -
6 a 10 12 14 16 18 20 22 24 26 28 30
Ey (MeV)
117Sn Mono 75Be6 , 69Pul
a) o(Y,n)+a(Y,pn)b) o(Y,2n)+o(Y,p2n)
c) o(Y,3n)
(nib)
(nib)
240
180
120 "
60
0
120
90
60 -
30
0
• 1 •
-
-
I 1
1
. 1 .
• — 1 — —
-
-
tir.n)
. i .
1
„•'
I
~ l —
I
' I
„.'"'i
~ — I —
1 1
ii
ii
. , .
• — I — '
I
Hi
i
ti
— I — •
1
I1
i
I
' i
? i |
i
—T"
11
i
1
a)
II. • 1.'l 1 '
- — 1 — • -
b)
|H | |lUl
i
-
-
-
i
— 1 — • —
-
-
i
OS
6 8 10 12 14 16 18 20 22
EY (MeV)
" 7 S n Mono 75Be6 , 74LeS
a) o(Y,n)to(Y,pn)bi o(Y(2n1+o(Y,p2n'l
75
2v3D.
pnHm7i
Oz
0
(lib)
0
nb)
240
180
120
60
0
t?0
90
60
30
- — i — i ——r
-
•
: /
, i i
—'—i—•—p—'—i—
i i i
' ' \
i
1 '
11
\
\
i
' •
jllilil1!l/ '
i—'""I1 • -
ai
-
i jijiu
I I .
1 • i •
bl
-
!i ,111 'i
" n i . i
"8
"Sn Mono 7SBe6 , 74Le5
a) o(Y,n)+o(Y,pn1
10 12 H 16 18 20 2?
1:Y CMCV)
21.0
180
(mb) ™
60
0
120
90
(mb)60
30
0
32
o »
(mb) 16
8 -
s\
J \
MHZi • i • i • - r " i - \ - r~" T
b)
c)
T . .... . j \10 12 K 16 18 20 22 21. 26 28 30
EY (MeV)
"Sn Mono 75Be6 , 69Fu1
a) o(Y,n)+o(Y,pn)b) a(ytZn)*o(
c) o(Y,3n)
(ml))
a
(mb)
(mb)
6 8 10 12 H 16 18 20 22 ?<• 26 28 30
9Sn Mono 7SBo6 , 69PU1
a) o(Y,n)+o(Y,pn)b) o(Y,2n)*o(
c) o(Y,3n)
0 0
O
&
mtnJOVICO
Oz
Sn
CN
GP
G2N
CNP
G2P
GA
Sn
CNGP
G2NGNP
G2P
GA
Sn
GN
GP
G2NGNP
G2PGA
A =
10.8
7.5
19.0
17.6
12.9
1.8
A =
6.99.4
16.516.2
16.9
3.8
A =
8.8
11.4
15.019.8
11
5.7
112 (1.0)
35.0 mln, EC, B*
2.83d, EC7.6 mln, IT4.15h, EC
4.9h, EC69 mln, B\ ECS
S
117 (7.7)
S14.10s, 8"54.1 min, B"; 2.S5.1E+14y, B"1.i9h, IT, B"
53.38h, B"44.8d, B"9.3E+15y, B"14y, IT
122 (4.6)
27.06h, B"55y, B"30.0s, B"3.8 mln, 8", ITS44.4s, B"3.0s, B"50.80s, B"50.3 mln, B"
A
10
8
18
17
14
2
16s,
A
8.
12.
14.20.
20.6.
=
.3
.5
.1
.9
.6
.6
114 (0.7)
1.151E*2d, EC21 min, IT, ECS; 99.5 mln, IT
S
14.4 mln, EC, 0*, B"20.9 mln, ITS
S
A = 118 (21.3)
9.3 S; 14.Od, IT10.0 M2.3 min, B"
IT 1.93h, B", IT16.3 S18.8 14.10s, B"
54.1 min, B"; 217.5 S
4.1 S
124 (5.6)
5
1
40
57
1.290Et2d, B"40.1 mln, B"5.98s, B"
48s, 6'S1.5s, B"9.2s, B"
5.78s, B"50.80s, B"
A
7
8
17
16
15
3
=
.5
.7
.9
.0
.6
.2
.16s,
115
S
71,49.1.
21s;
9.14ys;
IT
(0.
9s,51d,
.4)
B~, EC, B*IT, EC
151E+2d,mln,99.
3E+1
48.
A
69
1516
18
4
IT,5 min
I5y, B. IT6 min
= 119
.5 S
.9 4.8.
.8 S;
.5 42.1.
.2 2.3.
.4 53.44.
ECEC, IT
1"
, IT
(8.6)
35 mln,5s, IT,14.Od,
3 min,93h, B"42h, B"4h, B"38h, B"8d, B"
A
9
9
17,
18.
16.
3.
BB
=
.6
.3
.1
.3
.1
4
*
ITB"t IT
116 (11.7)
S
5.1E*4.49hS
71.9s,49.51dS
S
A =
9.110.7
15.619.0
19.0
1.8
I4y,, IT
B~,, IT
120
s;2.118.0s
, B"
EC, B*, EC
(32.4)
2.50E*2d, ITmin, 6"mln, B", IT
4.35 rain, B"8.5s, IT, B"; 50s, B'
50.3
S
mln, B"
>
-i1
0
(mbl
(mb)
a
(mbl
2«,0
180
120
60
120
90
60
30
32
24
16
8
0
• I -
-
/
. /
) ' V " . .
— ' — 1 — 1 — —
-
_
-
-
' 1 1
1 • 1 • 1 • I • I . • I
/ \ al
•
, 1 ' , " " . , . < " , " l ' . '
-i——i • i — i — • i —i—•—r
b)
1 Yl' \
;. %i
c)
i *\ ' t i i i " r
i '
-
-
urn— i —
-
-
i •
f71 J h
jJli
10 12 H 16 18 20 22 U 26 28
EY (MeVl
20Sn Mono 75Bc6 , 69Fu1
a
(mbl
0
(mbl
2;o
180
120
60
0
120
90
60
30
0
v
-
-
-
„'''"'"''"\yn)
1
-
_
-
-
i
. i,i
i
,'
/
/
1 1
1 1
'tiu J
1* B<I1,
1•l
\
1
II"I
i
ii1'i\
j • i
a)
" ' " " 'II '
' """" l i .
1 1
bl
•ili- l
i
' , '
-
-
-
H
i
-
-
>l.M
i
10 12 14 16 18 20 22
EY (MeV)
0Sn Mono 75Be6 , 74Le5
a)bl
to
g.tn
m70ViVI
O
ai o(bl o(cl o(Y,3nl
210
o 180
(mb)i20
60
0
120
90a
30
-
-
-
-
( M i
. . .
•
• .
i i
, • ' ' ' • • , ,
1 1 . 1 • ! —
. "I
H,
ft,!a)l . i I I
al
-
-
- , — . — , — . —
b)
\ ;
' i8 10 12 U 16
Ey (MeVI
l2"Sn Mono 75Be6 , 74LeS
a) o(Y,n)+o(Y,pnlbi o(Y,2nVo(
20 72
(mbi
21.0
180
120 -
60
0
120
a 90
Onbi
(mbl
32
n16 -
„
-
-
-
-
-
' I , . . ,
-
Sin
A*
MI
i
«
ii
in
/in
*v
in
»i . ,
IT.I»
il^S1 '1!1
uJ
''4,111
a)
-
"llll1 || !||
b)
-
jjiiUltVWM
c
\ 18 10 12 u 16 18 20 22 2*. 26 28 30
Ey (Me\D
12l)Sn Mono 75Be6 , 69Fu1
a) o(Y,nl+o(Y,pn)
bl o(Y,2nl+o(Y,p2nl
c) o(y,3n)
5
Antimony
Sb natural Mono 7SBc6 , 74Le5
a) o(y,n )
b) o(Y,nl+o(Y,pnlc) o(Y,2nl+o(Y,p2n)
Sb A = 121 (57.3) A = 123 (12.7)
9.2 15.89 rain, EC, B* 9.0 2.681d, B~, EC,5.76d, EC
CP 5.8 SC2N 16.3 38.Oh, ECCNP 11.9 S; 2.50E*2d, IT
C2P 16.5 2.1 mln, B"18.0 min, B", IT
GA 3.1 12.3 rain, 6"1.93h, B", IT
M.2 mln, IT6.6 S
15.8 S15.1 27.06h, B"
55y, B"18.0 30.0s, B"
3.8 mln, B", IT3.9 2.1 mln. B"
18.0 min, B", IT
(mb)
a
(mbl
(mbl
320
180
120
60
U
320
180
120
60
0
80
60
40
20
0
• • • • •
/
'ir.-l
-
-
-
_
1 '
-
-
-
i i
I ' T • • T1 • 1 - 1 — 1 •
\
I I I 1 1 , 1
_.••".. bl
;
1 1 1 1 1 1
cl
i . i . i . i . i . i .
10 12 H 16 18 20 22 24
EY (MeVl
t
Tellurium
(rabl
(mbl
21.0
180
120
60
0
240
180
120
60
0
1—•—i—"—i—•—i
6 8 10 12 U 16 18 20 22 ?4
Ey (NteVl
0
(mb)
120
90
60
30
0
• t • i • i • i • i •
t
\y.t) lr,wt i i i i .
i • i • i • i •
c l
' ' l ' 1 1
I I i i
6 8 10 12 tt 16 18 20 22 24
Ey (MeV)
Te natural Ntono 75Be6 , 74l.e5
b) o(Y,nl+o(Y,pnlc) o(Y,2n1+o(Y,p2
O
2
t3a.
VIO
Te A = 120 (0.1) A = 122 (2.5) A = 123 (0.9) A = 121
CH 10.3 i6.O5h, EC, B* 9.8 16.8d, EC4.68d, EC 1.54E+2d, IT, EC, 6*
GP 7.2 38.Oh, EC 8.0 S
G2N 17.9 6.00d, EC 17.0 S
GNP 16.8 3.5 rain, EC, B* 17.3 15.89 min, EC, B*5.00h, EC, B* 5.76d, EC
C2P 12.3 S 13.8 S
GA 0.3 S 1.1 S
6.9 S
8.1 2.68id, B', EC, 8*4.2 mln, IT
16.7 I6.78d, EC1.54E+2d, IT, EC, B*
14.9 S
14.5 27.06h, 8"55y, B"
1.5 S; 2.50E+2d, IT
9.4 >5E*13y, EC1.197E*2d, IT
8.6 S
16.4 S
17.5 2.681d, 8", EC, B*4.2 mln, IT
15.2 S
1.8 S
Te A = 125 (7.0) A = 126 (18.7) A = 128 (31.7) A = 130 (34.5)
CN 6 . 6 S
CP 8.7 60.20d, B"93s, IT, B"20.2 mln, IT
C2N 16.0 >5E+13y, ECCNP 15.2 S
C2P 15.8 1.290E+2d, B"40.1 mln, B
GA 2.2 27.06h, B"55y, B'
9.1 S; 58d, IT
9.1 2.71y, B"
15.7 S17.8 60.2Od, 8"
93s, IT, 0"20.2 min, IT
16.4 S
2.6 S
8.8 9.35h, B"1.09£+2d, IT, B"
9.6 3.91d, B"
15.1 S18.0 12.lid, B"
19.0 min, B", IT
17.6 1E+5y, B"
3.2 S
8.4 69.5 mln, B"33.5d, B', IT
10.0 4.41h, B"
14.5 1.54E+24y, B" B"18.0 9.10h, B"
10.0 mln, B", IT
18.5 59.3 min, B"
3.8 1E+5y, B"
H
t
746 FORKMAN and PETERSSON
'm
I I 1
I I I "
>•*
O O O O O
S !£ 2
-i D E
0
(mb)
80
40
20
0
-
-
-
'(Ml
A1,,,,, /
c l
ll'lll 1 1 1
' i l l
--
H
0
Cmbl
no
60
1,0
20
0
8 10 12 U 16 18 20 22 2t 26 28
E Y (MeVl
1 2 7 1 Mono 75Bc6 , 66Br1
a) o(YiiO
b) o(y,n)+o(y,pn')
c) o(Y,2n)+oC
I A = 127 ( 1 0 0 )
CN 9 . 1 1 3 . 0 2 d , EC, B*, B"GP 6 . 2 SG2N 16.2 6O.25d, ECCNP 15.3 S; 58d, ITG2P 15.3 2.71y, B"GA 2 . 2 S
20 -o
drib)
8 10 12 H 16 18 20 22 2<. 26 28 30
E Y ( M e V l
127I Mono 7SBe6 , 69BeS
a) o(Y,nt)
bl o(Y,n1to(Y,pn)
c) o(Y,2n)+o(Y(p2n)d) O(Y,3II)
5
748 FORKMAN and PETERSSON
\
; . /
i i i i \
1 1 1 1
- s |
.1 *". \*
: " \
I I I !
S> S orri rsi *—
a>
O, r
0
(mb)
0
(mb)
80
60
40
20
0
25
20
15
10
5
0
I
I 1 ' 1 ' 1 1 1 , ,
e l
d)
6 10 12 11 16 18 20 22 21 26 28
(Me\D
60 -o
(nib) 1.0
20
0
-
_
-
-
1 ' 1 ' 1
(
ni
' /
'lr.2il
V1
c)
l ( i -
1
i
8 10 12 14 16 18 20 22
F:Y (MeV)
l 33Cs Mono 75Be6 , 74Le5
a) o(Y,nt)
b) o(Y,n)+o(Y,pn)
c) o(Y,2n)+o(Y,p2n)
5
13)Cs Memo 75Bc6 , 69Be101 , 74Le5
a) o(Y,n t )
b) o(Y,n)*o(Y,pn)
d) o(Y,3n)
Ca A = 133 ( 1 0 0 )
CNGP
9.0 6.l)7d, EC,6.1 S
G2M 16.2 9.688d, ECGNP 15.0 S; 11.77d, ITG2P 15.2 S.OHOd, 0"CA 2.0 1.57E+7y, B"
I/I
o
Barium
(mb)
(mbl
300
200
100
o
300
200
100
0
1 I
-
-
-
-
lr.«)
1 I I 1 1 I I '
A ai .
.•y •
O
2
g.
PI
JO
O
(lib)
80
60
40
20
0
16
12
U
4
-
-
tail
-
-
T • -r • i • I •
I1'"''!1 ' fini
i
T ' 1 ' 1 •—1 *~
'. ' ' ' i . 1 .
i • ' • - • '
cl
''""•"A1, -i .. , ''M'l .
T—' 1 ' | —1
d)
1 ,
-
-
(».31,fll||J|
8 10 12 H 16 16 20 22 24 26 28
Ey (MeVl
"'Ba Mono 75Be6 , 70Be1
al o(Y,nt)b) a(Y,n)+o(y,pn)cl o(Y,2n)+o(Y,p2nldl o(y,3nl
6 8 10 12 1*. 16 16 20 22 2 k
EY (MeVl
Ba natural Mono 75Be6 , 71Be5
al o(Y,ntlb) o(Y,nl+o(Y»pnlcl o(Y,2nl+o(Y,p2n')
o
Ba
GN
CPG2NGNPC2PGA
Ba
CNGP
G2M
GNP
C2P
GA
A =
10.2
7.018.216.712.00.6
A =
7.08.3
16.4
15.1
14.8
1.9
130 (0.
22
3223SS
.20h,
. 1h,
.th.
.43d,
1)
EC,EC,EC,EC
.62 min,
135 (6.
S221038S
52S
,O62y.90h,.66y,.9h,
.245d
. 19d,
6)
. B"ITECIT,
. B"IT
; 11.77d,
A
8* 9B*B* 7
17B \ EC 17
131
A =
9.1, EC 8.5
16.1EC
17.4
15.4
IT 2.1
132 (0.
.8
.7
.3
.0
.1
.0
12.Od14.6
1)
I, ECmin,
9.688d,S
29.9SS
136 (7.
S2
53S
22S
S
; 28..95E+min,
.062y
.90h,
min,
9)
7h,6y,IT
, B"IT
; 0.29s,
ITEC
EC,
ITB"
, EC
IT
a*, B"
A =
6.98.7
16.0
15.4
15.8
2.5
A = 134 (2.
9.5 1O.66y,38.9h,
8.2 S16.7 S17.1 6.474d14.3 S1.5 S
137 (11.2)
S; 0.31s, IT13.00d, B"19a, ITS; 28.7h, IT
2.95E+6y, B"53 min, IT9.1O4h, B"15.6 min, IT,5.245d, B"2.19d, IT
4)
ECIT,
, EC
B"
EC
, B",
A =
8.69.0
15.5
17.3
16.4
2.6
B*
138 (71.7)
S; 2.551 min, IT3O.17y, B"
S; 0.31s, IT
13.00d, B"19s, ITS
S; 0.29s, IT
6»aQ.
mHm70vOz
Lanthanum
'La Mono 75Be6 , 68BeS , 71Be5
a) aly.n^
b) o(Y,nl+o(Y,pnl
cl o(Y,2nl+o(Y,p2nl
300
a 200
(mb)100
0
300 "
o 200
(nib)100
/ \
" • " '" • 2"
Af i
X •
" • " ' I U i |
-
-
S 10 12 14 16 IB 20 22 24 26 2B 30
La A = 138 (0.09) A = 139 (99.91)
(mbl
3
1 10 12 14 16 18 20 22 24 26 28 30
Ey (Me\O
GN 7 . 3 6E+My, EC 8 . 8 1.12E+11y, EC, B"CP 6 . 0 S; 2 .551 min, IT 6 .2 SC2N 16.6 9 .87 min, EC, B* 16.1 6E*4y, ECGNP 12.9 S; 0 . 3 1 s , IT 11.8 S; 2 .551 min , ITG2P 1M.7 13-OOd, B' 15.2 3 O . 1 7 t y , B"
19s, ITGA 2.0 2.062y, B", EC
2.90h, IT2.0 3.0E+6y, B"
53 min, IT
Cerium
a
(mb)
o
(mb)
(mb)
300
200
100
300
200
100
80
60
1.0
20
't'.'l 'IMl)
a)
i .3")
: AW' M '('.»)
-
-
r |
I rft
b)
-
I i il
c)
""lllllll "'('.31)
(mb)
400
300
200
100
0
A ^..jfrt.^-^
12 16 20
EY (MeV)
"*0Cc Brems 79Sh1O
o(Y,n) 68Be5 , 76Le5 ,66Br1 , 71CaS
o(-r,Po+p,) 71Sh1 , Sa3O
O73
S>
6>aa.mtn
enO
0(rob)
10 14 18 22 26
E Y (MeVO
30
Ce natural Mono 75Be6 , 69Be5 , 71Be5
a) o(Y,ntl
bl o(Y-n)+a(Y,pn)
c) o(Y,2nl+o(Y,p2n")
dl o(Y,3nl
Ce A = 136 (0.2) A = 138 (0.3) A = 110 (88.4)
GN 10.0 I7.76h, EC, 0*20s, IT
CP 6.9 19.Mh, EC, B*G2N 17.9 75.9h, ECCNP 16.6 6.67 mln, B*. ECG2P 12.1 SGA O.I) S
9.6 9.Oh, EC, 8'3!).l)h, IT, EC
7.6 6E+l)y, EC17.2 S16.9 9.87 min, EC, B*13.2 S; 0.31s, IT1.0 S
9.2 1.372E+2d, EC56s, IT
8.1 S16.7 S16.9 1.12E+11y, EC,11.3 S1.6 S; 0.31s, IT
A = 142 (11.1)
7.2 32.55d, 6"
8.8 3.9Oh, B"12.6 S15.6 1)0.27h, 8'15.8 12.789d fl"-1.1 S
--J
Praseodymium
350
250
(nib) 150 -
300
200a
(mb)100 -
-
J
-
• ,
. . • • • '
A
• i ,• {
ii
Si,
. ~V>.!
M l '
a)
,
bl
II
(mbi
350
250
150
50
0
^ /
/
i i
i i i i • -
10 12 14 16 18 20 22
Ey (HeVI
l l l l P r Mono 7SBe6 , 70Su1
o(Y,n ) ; (Y.pnl no t inc luded
50
OZ
0
(mb)
a
(mb)
80
60
10
20
0
20
15
10
5
u
-
MM)
-
-
-
~Mr..)
8 12
—i—'—i——r—'—r——I-"*1 r
'ill,'l ' ll'l
111 PI,!,I 1 I I I111.1 !| IIi ipn) (>.»)
' |».M) C."
1 • 1 . |
16 20 21
EY (MeV)
c)
-
Lii-iH
-
1 "
d)
1• H
-
i -
-
-
1I . i
350
250
0
(nib) 150
50
0
28 32
300
l"'Pr Mono 75Be6 , 66Br1
a) o(Y,n 1
b) o(Y,nl+o(Y,pn)
el o(Y,2ri')+o(Y,p2n')
d) o(Y,3nl
(mb)
lPr Mono 75Be6 , 71BeS
111 lPr Ntono 75Be6 , 72Yo
o(Y,n)+o(Y,pn)+2o(Y,2n)
"O
Lorentz parameters for the Pr data from 83Bo5
Melbourne11
LLL1
Saclay3
General Atomic11
Il l inois5
Heidelberg6
(McVl
15.15+0.1
15.16+0.08
15.1 +0.1
15.23
15.36
1S.4 +0.1
r(.MeVl
3.58+0.15
4.49±0.05
4.26±0.05
4.00
4.07
3.9 +0.2
(mbl
4OO±23
320+29
350+15
341
332
396+24
(MeV/b)
2.26+0.18
2.27+0.14
2.35+0.13
2.14
2.12
2.43+0.27
Fitting interval: 12-19 MeV except for Heidelberg (Unknown)1 83Bo5 Brems
quasi-monoonergetic photons
tagged photons
72Dr5 Brems
O
wJOv>C/l
O
Pr
CNGPG2NGNP
C2PGft
A =
9.15.2
17.311.1
13.11.2
111 (100)
3.39 min,S1.11h, EC,1.372E+2d,
56s, ITS6E+1y, EC
EC, B*
8*EC
PART 4-1 759
See overleaffor the graphs of neodymium
-oo
(mb)
IMeodymium
Nd i s o t o p e s Mono 74CaS
al 150Nd a(Y,n)+a(
bl l l i eNd
c) " " N d
dl l l l 5Nd
el 1'"1Nd
f) " 3 N d
g) " ' N d
o
(nib)
200
100
0
0
0
0
0
0
n
- a")
~ b l
—-•
- £ -I"
- n—
• • , - , . . ' •> • , ,
- - ' • ' *'•
Jy, i , , i
-
-
• ' • —
'i,
'••i.. —
' . _
'i •
• • . - . . —
. i . i .
12 16 20
EY (MeV)
300
o 2 0 0
(nibi 100
1 1
-
1 " T
^ - (
1
•-..
... ..,.. .
•i•<
s
a)
-
ti
ojo
3
am
C/5
O
a
[mb)
a
(mb)
225
ISO
75
120
80
(0
Q
'(»..) '!>.»! L.3.1'
v',»vr ** Hi
*
• i i i t i i .
i. 6 8 10 12 H. 16 18
Ey (MeV)
Nd natural ftono 75Be6 , 71Be5
a)b)c)
0
(mb)
10
30
20
10
0
_
-
ini
8 10
i
12i
V.
BY
I
16(MeV)
b)
,|
l l 'II
18
-
Il lI I
i
20
2Nd Mono 75Be6 , 71Ca5
a) o(Y,n)+o(Y,pn)b) o(Y,2nl+o(
(mb)
300
200
100
012 16 20
EY (MeV)
1112Nd Brems 79Sh1O
O O(Y,P)
• o(Y,n) 68Be5 , 76Le566Br1 , 71Ca5
•••• o(Y,Po+P, 1 71Sh1 , Sa30
1
a
(mb)
a
(nib)
300
200
100
80
60
10
20
0
-
-
-
-
-
-
(T.I)
'"I'I
li '
Ill'H11
II
al
bl
l l ' l ' l ,!, -1 | "
-
»)6 0 10 12 H 16 18 20
EY ( M C V )
lll3Nd Mono 75Be6 , 71CaS
a) o(Y,n)+o(Y,pn1bl oiY.^ni+oC^.pZnl
0
(nib)
0
(mbl
225
150
150
100
50
0
n
J*u
/
-
-
-
\
HI1|
' l
II '
/ '''"I1 _1
6 8 to 12 K 16 18 20Ey (MeVl
l""Nd Mono 75Be6 , 71Ca5
a) o(Y,n)+o(Y,pnl
bl o(Y,2n)to(
\O
>
M3
mw
CO
O
225
«0
150
100 -
50
0
ai
"I I
•y
bl
"I,
' » » • » • )
I, 8 12 16 20
Uy (MoV)
" sNd Mono 75Be6 , 71CaS
b) o(Y,2n)+o(Y,p2n)
Cinb)
""Nd ^ n o 75Be6 , 71Ca5
b) o(y,2nl*o(Y,p2nl
JO
a
(mb)
0
(mb)
225
150
75
200
150
100
50
0
-
-
II1"
-
-
-
' lr . i l
i i
1 '
Ai1" \
1
i1
i
,1
l l
i i
a)
-
I 'I '-I-
'i b )UN,
' l p
-
8 10 12 14
Uy (MeV)
Mono 75Be6 , 71Ca5
0
(mb)
0
mb)
225
150
75
0
200
150
100
50
0
r • i • i
-
Hi1
ii
(r,i)
-
-
-
'(r,o)
1 I . I
I ' 1
11
i i n .„ • " ' ",'
i'
I I
i • i •
a)
-
"'l l ' l1 "
(r,3»)
bl
-
1
' • ' H i , -
'('.)•)i i
g 10 12 14 16 18 20
Ey (MeV)
"Nd Mono 75De6 , 71CaS
o7>
S>
a.
mHin
O
a) o(Y,n)+o(Y,pn)bl o(v,2n)+o(Y,p2n)
a) o(Y,iO+a(Y,pn)b) o(Y,2n)+o(Y,p2n)
Nd
GN
CP
G2N
CNP
G2PGA
Nd
GNCP
G2NCNP
G2PGA
A =
9.8
7.2
17.9
16.6
12.50.8
A =
5.88.0
13.613.7
11.1-1.6
112 (27.16)
2.50h, EC, B*61s, IT, EC, 0*S
3
3
SS
11!
2.17.7.S13.
33.
.37d, EC
.39 rain, EC,
i (8.29)
1E*15y, a30 min, B*2 min, IT, B
59d, 8"
Oh, B"32.55d, B"
B*
A
78
1315
15-1
A
6
7
15
13
13-0
=
.6
.6
.3
.5
.1
.2
=
. 1
.5
.9
.1
. 1
.5
iie
S5.
2.17.7.2.S
113 (12.18)
S
19.2h, B", EC11.6 min, IT2.50h, EC, 8'
61s, IT, EC, BS
32.55d, B"1.372E+2d, EC
56s, IT
> (17.19)
98h, 6"
1E»15y, a30 min, B2 min, IT, 0"815E+2d, B"
A
79
1215
16-0
A
7
8
13
15
13-1
=
.3
.2
.6
.9
.2
.6
=
.8
.0
.9
.3
.8
.9
111 (23.80)
S
13.59d, B"
S
19.2h, fl", EC11.6 min, ITSS
118 (5.75)
1013
S21
132
•98d, B".6 min, 8
.0 min, 8
.9 min, B"
.815E+2d, B"
A
79
1216
170
=
.1
.6
.1
.5
.6
.1
150
1.2.
S2.
18s13.
(5.63)
73h, 8"3 min, 8"
30 min, B"
. 89 min, 8"
"8s
O
Samarium
o
(mb)
300
200
100
0
300
o 200
( m b ) ioo
0
-T 1 • r—' 1—-• r
a)
.1 \
y """"Mlil'(Ml
bl
200
100
0
(mb)
' 1
a)..-'
d)
el .
• i •
r1' .
. ' • • /
r
rt's'"''-'K' • • • _
"A
I.
— i — • — i — • —
-
t
*1
I
10 12 14 16 18 20 22
EY (Me\O
Sm isotopes Mono 74Ca5
a) 15"Sm o(Y,nHo(Y,pn)+o(Y,2n)bl 152Sm — ii —cl l50Sm —II —dl 14eSm —« —e) 1-"Sm — • —
T1
o
so.>«m
m
O
0
Gnb)
150
100
SO
0
20
fab)
X( r , l . ) f u l i )
dl
I 8 12 16 20 2<>
E Y CMeV)
Sm natural Mono 75Be6 , 69BeS
al o(Y,nt)bl o(Y,n)+o(Y,i»n)
cl o(d) o(Y,3nl
0
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bl o(Y,2n)ta(Y,p2n)
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1 2 . 6 , B", EC, B*
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13.5 S-0.9 S
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6.1 S7.6 8.5y, B~, EC
16 min, IT15.1 2.H6E+2d, EC
11.1 16.8h, 8"-0 .1 87y, B'
t
Gd A = 156 (20.6) A = 157 (15.7) 158 (21.8) A = 160 (21.8)
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a
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0
(mb)
250
200
150
100
50
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250
200
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0
(mb)
0
(rab)
0
(mb)
250
200
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50
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b) o(Y,nl+o(Y,pn)
c) o(y,2n1*o(y,p2n)
d) o(Y,3n)
Tb A = 159 (100)
CN 8.1 1.5E*2y, EC, 0"10.5s, IT
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0 0
0
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0
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320
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80
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320
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300
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b) oCY.nltoCYipni
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Targe t 1 Beam
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GN 8.0 29.0 mln, EC, 8 '37 mln, IT
GP 6.2 SG2N 11.7 33y, EC
1.093, ITGNP 13.9 SG2P 11.8 19.5 min, B"CA -0 .1 6.9Od, B'
780 FORKMAN and PETERSSON
=£ -I
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6.7s, IT 1.09s, ITG2N 16.5 28.58h, EC 15.8 SGNP 1M.9 25.6 min, EC, B* 15.3 15 mln, EC, B*
5.02h, IT, B* 68 mln, IT, EC, B*G2P 11.2 S 12.3 SCA -1.7 S -1.3 S
Er A s 166 (33.1)
CN 8.5 10.3th, ECGP 7.3 S
A = 167 (22.9) A = 168 (27.1) A = 170 (It.9)
6.1) S7.5 26.83h, B"
1.2E+3y, B"G2N 15.1 S 1t.9 10.3th, ECGNP 15.3 29.0 mln, EC, B" 13.8 S
37 rain, ITG2P 13.5 S 1t.3 2.33h, B~
1.26 mln, IT, B"GA -0.8 S -0.7 S
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i.2E+3y, B"15.0 81.5h, B"
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13.3 S15.3 2.98 mln, 6"
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320
210a
(mb) tt0
80
0
300
200
100
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0
(nib)
150
100
50
0
40
30
20
10
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GN 7 . 7 3 . 3 1 y , EC, B*1.1(2E+2d, I T , EC
GP 5 .5 SG2N 11.H l | .99E+2d, EC
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c) o(Y,2n)+o(y,p2n)
d) o(y,3n)
00
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300
250
200
0 150
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50
300
250
200
150
100
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400
300
200
100
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al o(Y,n t)
bl o(Y,nl+o(Y,pnl
cl o(Y,2nl+o(Y,p2n}
150
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(mb)
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10 14 18 22 26 30 34
Ey (MeV)
Ta A = 180 (0.012) A = 181 (99.988)
CN 6.6 6.65E*2d, EC 7.6
GP 5.7 S; 18.7s, IT; 25 . Id , IT 5.9C2N l i t .5 9.25 min, EC, B* 14.2CNP 11.8 S; 1.0s, IT ; 3 'y , IT 13.3C2P 13.3 28. t min, B" 13.9
23 min, B"GA -2.1 3.79E+1Oy, B" -1 .5
3.68h, B"
>E+I3y, B", EC8.1h, EC, B"S6.65Et2d, ECS; 18.7s, IT; 25.1d, ITt.59h, B"
6.71d, B"1.6O5E*2d, B", IT
l e l T a Mono 75Be6 , 68BeS
a) o(Y,nt1b) o(Y,n)to(Y,prV)
c) o(Y,2n1+o(Y,p2n')
d) o(Y,3n)
Tungsten
400
0 300
200
100
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400
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(mb)200
100
0
240
180
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w
GN
GPG2NGNP
G2PCA
A =
8.5
6.615.111.5
11.8-2.5
180 (0.1)
37.5 min,6.1 rain,6.65E+2d
21.5d, EC9.25 min2.1h, ECS; 1.0s,S
ECIT,, EC
, EC,
IT;
EC
B*3iy, IT
A = 182 (26.3)
GN 8.1 1.210E+2d, EC
GP 7.1 S
C2N 11.7 SGNP 11.7 >E+13y, B", EC
8.1h, EC, B"
G2P 13.0 S; 5.5h, IT
A = 183 (11.3)
6.2 S
7.2 1.15OE+2d, 0"0.28s, IT15.8 min, IT
11.2 1.210Et2d, EC13.3 S
A = 181 (30.7)
7.1 S; 5.3s, IT
7.7 5.0d, B*
13.6 S11.6 1.150E*2d, B"
0.28s, IT15.8 min,
13.5 12.i5d, B" 11.3 9E+6y, B"62 min, B", IT
CA -1.8 S; 1.0s, IT; 31y, IT -1.7 S; 18.7s, IT; 25.1d, IT -1.7 S
186 (28.6)
7.2 75.Id, B"1.66 rain, IT
8.1 50 min, B"
13.0 S15.2 8.7h, B"
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cl o(Y>2nl+o(Y>p2n)
0
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0
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0
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460
360
240
120
0
480
360
240
120
240
160
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460
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480
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d) o(Y,3n)
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480
360
240
120
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460
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4 8 12 16 20 24 28
E Y (MeVl
1 9 20s tono 79Be1
t
bl o(Y,nl+o(y,pnlcl o(Y,2nl+a(Y,p2nl<1) o(Y,3nl
al o(Y,n tl
b) o(Y,nl+o(Y,pnlc) o(Y,2nl+o(
dl o(Y,3n)
Os A = 181 (O.O2) A = 186 (1.58) A = 187 (1.6)
GN 8.9 13.Oh, EC, B* 8.3 93.6d, EC9.9h, EC, IT
CP 5.7 71d, EC 6.5 S
C2N 16.1 22.1h, EC 11.9 SCNP 11).2 12.7h, EC, B* 14.3 38.Od, EC
61h, EC 1.69E*2d, IT, ECC2P 10.5 S 11.9 S
GA -3.1 S -2.8 S
6.3 2E+15y, a
6.6 90.6th, 8~, EC2E+5y, IT
11.6 93.6d, EC12.8 S
12.1 75.Id, B"1.66 rnin, IT
-2.7 S; 5.3s, IT
Os A = 188 (13.3) A = 189 (16.1) A = 190 (26.1) A = 192 (11.0)
GN 8.0 S
CP 7.2 1.3E+10y, 8
5.9 S
7.3 I6.98h, B"18.7 min, IT
G2H 11.3 2E+15y, a 13.9 SCNP 11.6 9O.61h, B\ EC 13.1 1.3E+10y, B"
2E+5y, ITC2P 13.2 S 13.7 23.85h, fGA -2.1 S -2.0 75. Id, B"
1.66 min, IT
7.8 S; 5.7h, IT 7.6 15.Id, B"13.1h, IT
8.0 21.3h, B" 8.8 9.8 min, B"
13.7 S 13.3 S; 9.9 min, IT15.1 I6.98h, B" 15.7 3.1 min, B"
18.7 min, IT 3.2h, 0\ IT11.6 69.Id, B" 16.2 30 nin, B"-1.1 S -0.1 69.Id, B"
50
792 FORKMAN and PETERSSON
z- '
U —
—zz
1 •
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oa
O LA O
Au Mono 75Be6 , 62Fu101
t
bl o(Y,nl+a(Y,pn)
c) o(Y,2nl+o(y,p2n)
100
a ,0
(mb)
e
,Ti.20 fcO
. . • —i 1—
60 80 100 120 HO
EY (MeV)
(mb)
l " A u 79Pr5
12 16 20 21.
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1 9 7Au Mono 75Iie6 , 7OVeS
a) o(Y>n.)
c) o(Y,2n)+o(Y,p2n)d) o(Y,3n)
Eo. (all reaction channels)
Zo(Y.n.) flu A = 197 (100)
CM 8.1 6.18d, EC, 6*, 6"8.2s, IT; 9.7h, IT
CP 5.8 SC2N m.B !.829E*2d, EC
30.6s, ITGNP 13.7 S; U.O2d, ITG2P 13.9 2.3h, B~
3.8h, 8"GA -0.9 S; 10.6d, IT
Lead
(mbl
(mb)
SOO
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300
200
100
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300
200
100
0
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60
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a l o(Y,n 1
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TO
cl o(Y>2nl+o(Y,p2n1
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© <=> © § 1 - © © © ©LH © LT1
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o ^o u-i
2 " P b Mono 75Be6 , 64lla1
al o(Y,n t l
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c)
10 12 14
1-Y (MeV)
(mb)
208Pb Mono 75Be6 , 70Ve5
al o(Y,n t)
bi o(Y,n)+o(Y,pn)
cl o(Y,2n)+o(Y,p2n')
dl o(Y,3n)&H
2OBl'b Mono 75Be6 , 72Yo
Pb A : 201 (1.4)
CN 8.H 52.O2h, EC6.1a, IT0.48s, IT
CP 6 . 6 S
A = 206 ( 2 4 . 1 ) A = 207 (22.1) A = 208 (52.4)
8.1 1.4E+7y, EC
7.3 S
6.7 S
G2N 15.2 3E+5y, EC3.62h, IT, EC
GNP 14.4 12.23d, EC 11.83-77y, 8", EC
7.5 4.18 min, B"3.6 min, IT
14.8 S; 66 .9 min, IT 14.8 1.'IE+7y, EC
G2P 12.3 SGA -2.0 S
13.7 S-1 .1 S
14.0 S
14.7 5 .2 min, 8"-0 .4 46.76d, B"
7.4 S; 0.81s, IT
8.0 4.79 min, 8"1.3s, IT
14. 1 S
14.9 4.18 min, B~3.6 min, IT
15.4 8.2 min, 8"-0.5 S
Bismuth o73
soo400
o 300
(mb) 200
100
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Bl
GNGPC2NCNPG2P
GA
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7.53.8
1f.411.20.8
-3.1
209 ( 100)
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38y,S; 01.791.3sS
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400
300
200
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400
300
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A =
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232 (100)
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>
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5.3 2.116E+5y, a 6.1 6.75d, B"6.7 6.75h, B" 7.6 8.7 min, B"
1.175 min, IT12.1 1.59E+5y, a 11.3 2.3iEt7y, a
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(mb)
o
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300
200
100
225
150
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12.311.1
12.0-5.0
237 (—)
22.5h, EC,2.311E+7y1.16E-73,3.96£+2d,7.0UE+8y,
26 mln, IT21.2 mln,26.95d, 6"
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100
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50
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300
200
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808 FORKMAN and PETERSSON
REFERENCES TO SECTION 4
54Fel57Col
610rl662Dal62Ful62Ful0163Br 163So1363Zul64Ba564Brl64Del864Ful64Hal64Isl3
65Ha566Br 166Ke766Ful66Lol67Bel67Co768B&568BelO56BBe205
6BOw568Sul69Bel69Be569BelOl69Ful69Is2269Kel69WU1370Bal70Bel70Co870Me570Sul70Ve571A1171Bel
TtBi13
71Fa871Ful71Ku571Le5VIStil71Shl 1
71Wo872Be5
PHYS.PHYS.PHYS.CAN.PHYS.PHYS.PHY'S.PHYS.PHYS.PHYS.NUCL.PHYS.SOV.PHYS.PHYS.PHYS.PHYS.NUCL.NUCL.PHYS.
REV. 95(1954)776REV. 106(1957)300REV. 144(1961)834J. PHYS. 39(1961)1397REV.REV.REV.REV.LETTREV.PHYSREV.
PHYS.REV.REV.LETT,REV.PHYS,PHYS.REV.
127(1962)1746128(1962)2345127(1962)1273129(1963)27235(1963)149 A132(1963)751
G.A. Ferguson et alB.C. CookH.M. Serstenberg et al
G.M. Griffiths et alDodge et alFultz et alFultz et alBramblett et al
1al
w.s.s.R.N. Gorbunov et iR.W. Zurmuhle et
. R.
.C.
. C.
.L.
54(1964)549 J.E.E. Baglin et al133(1964)B869 R.L. Bramblett et alJETP 19(1964)1007 V.P. Denisov etal133(1964)61149 S.C. Fultz et al136(1964)B126 R.R. Harvey et al9(1964)162 B.S. Ishkhanov et al
LETT. 15(1965)727 B.L. Herman et al71(1965)305 V.N. Fetisov et al69(1965)241 E. Hayward et al148(1966)1198 R.L. Bramblett et al
IL NUOVQ CIMENTO 456(1966)273 F. Ferrero et alPHYS. REV. 143(1966)790 S.C. Fult^ et alPHYS. REV. 141(1966)1002 W.A.PHYS. REV. 162(1967)1098 B.L.IL NUOVU CIMENTO 51B(1967)199NUCL. PHYS. A121(1968)463 R.
PHYS. Al16(1968)632PHYS. Al17(1968)124LETT. 27B(1968)436PHYS. A122(1968)177REV. 176(1968)1366REV. 185(1969)1576PHYS. Al33(1969)417REV. 1/7(1969)1745REV. 1B6(1969)1255ACAD. SCI. USSR 33(1969)1594REV. 179(1969)1194 M.A. KellyLETT. 296(1969)359 C.P. Wu etREV. Cl(1970)165 l.M. BarbourREV. C2(1970)2318 B.L. BermanREV. LETT. 25:10(1970)685 B.C.PHYS. A148(1970)211 MeyerhofREV.
NUCL.NUCL.PHYS.NUCL.PHYS.PHYS.NUCL.PHYS.PHYS.BULL.PHYS.PHYS.PHYS.FHYS.PHYS.NUCL.PHYS.NUCL.PHYS.PHYS.NUCL.PHYS.NUCL.PHYS.PHYS.NUCL.NUCL.PHYS.
Lochstet et alBerman et alS. Costa et alBergere et al
R.C. Bearse et alN. Bezic et al
A.N. GorbunovD.B. Owen et al
R.E. Sund et alBerman et al
Bergere et alBerman et alFultj et al
B.L.R.B.L.S.C.
B.S.etaletet
. Ishkal
alal
. Cook etet al
hanov
al
et al
C2(1970)1129 R.E. Sund et alPHYS. A159(1970)561 A. Veyssiere et alREV. C4(1971)1673 R.A. Alvarez et al
C4(1971)723 B.L. Berman et alA172(1971)426 H. Bei1 et al348(1971)1 J. BirkholzA172(1971)437 P. Carlos et al
LETT. 27(1971)1016 S. Fallieros et alC4(1971)149 S.C. Fuitz et alA171(1971)384 S.K. Kunda et alA175(1971)609 A. Lepretre et al
4C( 1971) 1842 K. Shocia et alLABORATORY of NUCL. SCIENCE TOHOKU(•;. Shod a et al
REV.PHYSLETTPHYSREV.REV.PHYSPHYSREV.
RESEARCH REPORT ofUNIV. 4-1(1971)30PHYS. REV. LETT. 26(1971)907 A. van der Woude et alNUCL. PHYS. A179( 1972) 791 B.L. Berman et. al
PART 4-1 809
72Bi572Do872D> 572Kh572Ms872Th572Yo73.4142
73Au573Be42
NUL:L .PHYS.NUCL.NUCL.PHV'S.NUCL.
APPLICATIONS.73Bel42 PROC. of the INT. CONF
73Br44APPLICATIONS.
73C1573Hu573Mal373f1c373Ms473Ms573Pd42
73Sol473Til373Ve573Ye574Anl74Bel74Be574Brl74C«574CalO574Ch5
74De474Ful74L&574Ma574Sli574Va574Ve575Ah575A;<875bt!Q
75B&1575Del475Hu575Irl675K.u573Kn975K.U175Mcl75 I hi 1
75To33
PHYS. A189<1972>385 J. Birkhols*EV. LETT. 28(1972)839 W.R. Dodge et alPHVS. A181(1972)477 F. Dreyer et. alPHYS. A179(1972)333 A.M. Khan et alREV. LETT. 28(1972)847 E.D. Mshelia et alPHYS. A19fc(1972>89 B.W. Thomas et al
Unpublished UNIV. of ILLINOIS (1972) L.M. Young et alPROC. of the INT. CONF. on PHOTONUCLEAR REACTIONS andAPPLICATIONS. ASILOMAR (1973) 547 R.A. Alvarez et alNUCL. PHYS. A212(1973)221 R.A. finder1 et alPROC. of the INT. CONF. on PHOTONUCLEAR REACTIONS and
ASILOMAR (1^73) vol 1:525 R. Bergere et alon PHOTONUCLEAR REACTIONS and
ASILOMAR (1973) Vol 1:159 F. Beck et alPROC. of the INT. CONF. on PHOTONUCLEAR REACTIONS andAPPLICATIONS. ASILOMAR (1973) Vol 1:175R.L. Bramblett et alNUCL. PHYS. A213(1973)35B G.E. Clark et al
A215(1973)147 R.J. Hughes et al476(1973)433 C.K. Malcolm et alA213U973) J.J. McCarthy et alf. PHYSIK 261(1973)313 E.D. Mshelia et alA2O5(1973)581 E.D. Mshelia et al
PRCC. of Una INT. CONF. on PHOTONUCLEAR REACTIONS andAPPLICATIONS. ASILOMAR (1973) Veil 1:407 P. PaulSUV. J. NUCL. PHYS. 17(1973)1 YU.I. Sorokin et al
LET1. 466(1973)369 G. Ticcioni et alA1V9(1973)45 A. Veyssiere et alA206(1973)593 M.V. Yester et al
09(1974)1919 D.W. Anderson et alC10(1974)2221 B.L. Berman et alA227(1974)427 H. Bei 1 et al
REV. C9(1974)1901 D. Brajnik et alPHYS. A219(1974)61 P. Carlos et al
A225(1974)171 P. Carlos et alA235(1974)1
A.h. Chung et al (Data - J.U. Irish)ZEITSCHR1FT f. PHYSIK 271(1974)391 J. Devos et alPHYS. REV. C10(1974)608 S.C. Fultz et al
A219(1974)39 A. Lepretre et alJ.L. Matthews et alK. Shoda et alV.V. Varlamov et alA. Veyssiere et alJ. fthrens et al
NUCL. PHVS.PHYS. LETT.NUCL. PHYS.ZE1TSCHRIFTNUCL. PHYS.
PHYS.NUCL.NUCL.PHYS.PHYS.NUCL.PHYS.NUCL.NUCL.NUCL.
PHYS.PHYS.REV.REV.PHYS.
PHYS.PHYS.
A223(1974)221A221(1974)125A222(1974)548A227(1974)513A251(1975)479
NUCL. PHVS.NUCL. PHYS.NUCL. PHYS.NUCL. PHYS.NUCL. PHYS.NUCL. PHYS.PHVS. REV. LETT. 35(1975)501 P. A>;el e t a lATOMIC DA IA AND NUCLEAR DATA TABLES 15(1975)319B.L. BeriiianREV. of MODERN PHYS. 47(1975)713 B.L. Berman et alSUV. J. NUCL. PHYS. 22(1975)466 V.P. Denisov et alNUCL. PHVS. A238(1975)189 R.J. Hughes et alCAM. J. PHYS. 53(1975)802 J.D. Irish et alNUCL. PHYS. A247(1975)91 U. Kneissl et alNUCL. INSTR. and METHODS 127(1975)1 U. Kneissl et alPHVS. REV. 011(1975)1525 E. Kuhlmann et alPHVS. REV. 11(1975)772 J.J. McCarthy et alRESEARCH REPORT of LABORATORY of NUCL. SCIENCE TOHOKUUNIV. 8(1973)266 M.N. Thompson et alRESEARCH PEPURI of LABORATORY of NUCL. SCIENCE. TOHOKUUNIV. 8:2(1975)269 M.N. Thompson et al
810 FORKMAN and PETERSSON
76Br 176Cal76Le577Ba7770i577Shl278A1578Arl778Nol278Ta41
7BTh41
7BZul479 A11
79Bel79Dzl479Jol79Jul79Ju479Pr579Py579ShlO79Skl79Skl0179Ts579Wol8OAr46
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and VIRTUAL
REV. C21(1980)503 J.W. Jury et alPHYS. A339(1980)125 R. Sutton et alREV. C22(1980)2396 E. Van Camp et alFHYS. A357(1981)171 P.D. Allen et alPHYS. A357(1981>429 Y.I. Assa-f i r i et alo-f the INT. SCHOOL o-f INTERMEDIATE ENERGY- VERONA (1981> 65 C. Ciofi degli AttiREV. C24(1981)849 D.D. Faul et alJ. NUCL. PHYS. 33(1981)453 B.S. Ishkhanov
NUCL.
et alPROC. o-f the FOURTH INT. SYMPOSIUM on NEUTRON CAPTUREGAMMA-RAY SPECTROSCOPY and RELATED TOPICS - GRENOBLE(1981) 613 E.W. LeesNUCL. PHYS. A369(1981)141 R.E. Pywell et alNUCL. PHYS. A371(1981)318 P.J.P. Ryan et alPROC. o-f the INT. SCHOOL o-f INTERMEDIATE ENERGY NUCL.PHVS. - VERONA (1981) 3O7 K. ShodaPHYS. REV. C24(1981)317 L. Ward et alNUCL. PHYS. A376(1982)15 K. Bangert et alNUCL. PHYS. A37B(1982)317 P. Carlos et alPHYS. REV. C26(1982)777 J.W. Jury et alNUCL. PHYS. A388(1982)445 G. Odyers et alPHYS. REV. C26 (1982) 448 I). Ryckbosch et alZEIISCHRIFT f. PHYSIK A306(1982)139 A. Veyssiere et alPHVS. REV. C27(1983)1 B.L. Berman et alPROC. of the INI. CONF. on NUCL. PHYS. FLORENCE (1983)vol 1:350 P. Berkvens et alNUCL. PHYS. A406(1983)257 T.J. Boal et al
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(1983) 50 E. Kerkhove et al830t47 PROC. of the INT. CONF. on NUCL. PHYS. FLORENCE <1983)
VUL 1:347 P. Van Otten et al83Pyl PHYS. REV. C27(1983)960 R.E. Pawell et al83Ry5 NUCL. PHYS. A411<1983)105 P.J. Ryan et al83Su5 NUCL. F:HYS. A398 (1983) 415 R.A. Sutton et al83Zul PHYS. REV. C27(19B3)1957 D. Zubanov et al84As5 NUCL. F:'HYS. A413 (1984) 416 Y.I. Assa-firi et alSa3u Privatu Cuniinurii cation T. Saito et al
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