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B.A.R.C-686 0 00 3 GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION ANALYSIS OF COMPLEX Nal (Tl) GAMMA-SPECTRA FROM MIXTURES OF NUCLIDES by C. Rangarajan, LI. C. Mishra, Smt. S. Gopalakrishnan and S. Sadasivan Health Physics Division DHABHA ATOMIC RESEARCH CENTRE BOMBAY, INDIA 1973

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Page 1: GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION · 2015-03-30 · B.A.R.C-686 0 300 GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION ANALYSIS OF COMPLEX Nal (Tl) GAMMA-SPECTRA FROM MIXTURES

B.A.R.C-686

000

3

GOVERNMENT OF INDIAATOMIC ENERGY COMMISSION

ANALYSIS OF COMPLEX Nal (Tl) GAMMA-SPECTRA FROM MIXTURES OF NUCLIDES

byC. Rangarajan, LI. C. Mishra, Smt. S. Gopalakrishnan and S. Sadasivan

Health Physics Division

DHABHA ATOMIC RESEARCH CENTRE

BOMBAY, INDIA

1973

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T3.A.H.C.-686

GOVERNMENT OP INDIAATCMIC ENERGY COMMISSION

u•

ANALYSIS OP COMPLEX !JaI (Tl) . r,A?/MA-SFECTnA WXjUi MIXTURES OP

by

C. Rangarnjan, U.C. Mishre . Smt. S. Gopalakriehnan and S. SedaoivanHealth Thysics Divis ion

BHABHA ATCMIC RESEARCH CENTREBO1BAY, INDIA

1973

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ABSTRACT

The report describee methods o f gassa apestrua analys i s being

used In t h i s laboratory. The gamma spectra are taken with Hal (Tl)

d e t e c t o r s of d i f f e r e n t dimensions on various ault ichannel analysers .

The samples being analysed are airborne f a l l o u t r a d i o a c t i v i t y , surfaoe

d e p o s i t i o n s t milk ani other food s t u f f s and countrywide surface s o i l s .

These samples contain both natural gamma a c t i v i t i e s from t e r r e s t r i a l

sources and f a l l o u t r a d i o a c t i v i t y , mostly f i s s i o n products, due t o

nuclear explos ions . The methods of analyses described are spectrum

s t r i p p i n g , simultaneous equations and the l e a s t squares method. The

r e l a t i v e merits and demerits of the d i f f e r e n t methods and the parameters

of the instrument systems being used are a l s o g iven.

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ANALYSIS OP COMPLEX Nal (Tl) GAMMA-SPECTRA FROM MIXTURES 0? ITOCLIDES

by

G. Rangarajan, U.C. Mishra, Smt. S. Gopalakrishnan and S. Sadaaivan

1. INTRODUCTION

Scintillation spectrometers consisting of Nal (Tl) detectors of

various dimensions and multichannel analysers are being extensively used

far the measurement of samples containing mixtures of gamma-emitting

(1 2)nuclldes * . Though the method is simpler than the conventional

chemical methods,, the accuracy of the estimations is dependent on the

complexity of the gamma spectrum. The samples being analysed at this

laboratory include airborne radioactivity collected on filter papers,

rain-water, soil, food stuffs etc. This report describes the various

methods of apectrum analysis being used at this laboratory. Computer

programmes written in Fortran language used in these enalysas have also

been included.

2. COMPOSITION OP A GAMMA SPECTRUM

The gamma spectrum of a s ingle mono-energetic nuc l ide cons i s t s of

a f u l l energy peak, approximately Gaussian in shape, corresponding t o the

gamma energy of t h e n u c l i d e , and a cont inuous d i s t r i b u t i o n moBtly a t

ene rg i e s lower than t h e f u l l energy peak. The f u l l energy peak i s due t o

the complete absorp t ion of gammas w i t h i n the d e t e c t o r , e i t h e r by

photoelectric effect, or by multiple interactions of various types

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reeulting in complete absorption within the detector. The continuous

distribution arises due to events in which only a part of the photon

energy Is absorbed inside the detector volume while the photon carrying

the regaining energy escapes from the detector. The processes that can

give rlae to such interactions are the following:

a) Compton scattering in which the scattered photon

escapes the detector,

b) Pair-production events in which one or both the

photons escape from the detector (valid only for

thoae sources which emit gammas of energies greater

than 1.02 MeV),

c) Pair-production events occuring outside the

detector in which one or both the photons from

positron annihilation enter the detector,

d) Photons scattered by the materials outaide the

detector, such as lead shields, etc., into the

detector volume,

e) Photono degraded in energy due to self-scattering

in the sample material or by small anglt- scattering

events in the detector can,

f) "Bremsstrahlung" radiation in the case of high

energy beta emitters due to the stopping of betas

in the abnorbera placed between sample and detector

to prevent their entering the detector,

g) "Iodine Escape Peak" at lower energise due to the

escape of X-rays from the excitation of Iodine atoms

in the Nal crystal,

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h) "Summing" of two photon energies either due to

random summing of energies of two or more

scattered photons particularly in the case of

very active sources, or due to cascade emission

as in Co-60, in which case their contribution

extends from lower energies to the energy

corresponding to the sun of the two photon energies*

The last mode of interactions can give r i se to contributions in

the gamma spectrum at energies higher than the photopeak energy .

It i s evident from the above description that the gamma-apectrua

of samples containing a mixture of nuclidea i s complex. The most eooaon

nethod of analysing gamma spectrum i s to use the fu l l energy peak counts

of various isotopes for estimating their ac t iv i t i e s because the f u l l

energy peak i s generally characteristic of the isotope and i t i s in this

energy region that a better sample to background counts ratio i s

obtained. The background referred here i s not only the conventional one

due to cosmic-rays and terrestrial radiations but also the continuous

portion of the spectra due to other ful l energy peaks in the sample.

If the constituent nuclidea of a sample emit gamma rays of closely

spaced energies, i t ie often advantageous to select only a small portion

of the f u l l energy peak of each of them. This reduces tae region of

mutual overlap of adjacent peaks as shown in Figure 1, thereby improving

isotope counts to background ratio for each of the radionuclides. This

method of selecting fu l l energy peak regions for the anaJgrais has sons

disadvantages also . If the region selected i s too narrow, the counts

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summed are reduced giving r i s e t o poorer s t a t i s t i c s . Also, the

errors due to gain and threshold d r i f t s in the analyser can be

s ign i f i cant . Hence the s e l e c t i o n should be made i n such a way that

the effect of d r i f t s In the sr^alyser as wel l as overlap of the

adjacent peaks i s kept to a minimum. While s e l e c t i n g these energy

regions , i f an Isotopes emits more than one gamma rays , the moat

abundant gamma energy should be taken for a n a l y s i s . If there are

several gamma energies with comparable abundances, the highest energy

which i s l i k e l y to have least compton contributions from other nuc l ldes ,

should be se l ec ted .

3 . ANALYSIS OF GAMMA SPECTRUM

The choice of the method of analysis depends on the complexity

of the gamma spectrum, i . e . the number of nucl ides present i n the

sample and the computing f a c i l i t i e s avai lable . A number of a n a l y s i s

methods are in use at th i s laboratory. The simplest method i s the

spectrum stripping technique. This method i s used when the samples

contain 2 to 3 isotopes oaly with widely separated gamma energ ie s , a s in

the case of milk samples which contain mainly Cs-137 and K-40. In cases

where samples contain 5 to 6 or more nuclides (a i r f i l t e r s , s o i l samplen

e t c . ) and the gamma spectra have several c l o s e l y spaced overlapping

peaks, simultaneous equations or least squares method i s being used.

The following sections describe the above methods in deta i l and d iscuss

the ir re la t ive advantage mi disadvantages.

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3.1 Method of Spectrum Stripping:

The principle of the method for the analysis of milk samples i s

shown analytically in Figure 2. Curve (a) shows the gamma spectrum of

the milk sample as recorded by the analyser. Curve (b) shows the

background spectrum for the sample counting period. The background

subtracted sample spectrum i s shown by Curve (c) . A standard source

spectrum for K-40 i s taken separately. After background subtraction the

at 1.46 MeV i s normalized to the sample spectrum by multiplying the

standard spectra with a suitable factor (ratio of peek counts of source

to sample) so that the K-40 peak at 1.46 MeV in'the standard source

spectrum exactly coincides with that for the sample. This factor

multiplied by the K-40 content of the standard gives the K-40 activity

in the sample. The counts in a l l the loner energy channels are also

then multiplied by the above factor and th i s normalised K-40 spectrum i s

shown in the above figure by Curve (d) . Curve (d) i s then subtracted

channel by channel from Curve (c) giving Curve (e) which represents the

gamma spectrum due to Cs-137 activity of the sample. The photo-peak

counts of 0.661 MeV gamma ray in the above curve are compared with the

photo-peak counts of Cs-137 standard spectrum to get the Cs-137 content

of the sample*

In practice, the spectrum i s divided into as many regions as

the number of isotopes present. These regions are selected around the

total energy peak as described In the earlier section. The spectra

of the standard sources are taken and for each source, the counts in

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other regions as a fraction of counts in the total energy peak region

of that isotope are determined. These fractions are referred to as

the compton fractions of those regions. Thus if P.. are the counts due

to isotope J in region 1 and if P, are the counts in the total energy

peak region of the spectrum of isotope j , the compton fraction nt^,n

for region i due to isotope J is given by

f i3 " PiJAJ

If C are the counts due to sample in region i , they can be

expressed as

f i1 * P1 + f i2 ' P2 + f i i P i + •"• fiJPJ ° i

Where t.. i s unity.

Therefore for j isotopes, j equations of the above type can bs

solved.

To illustrate this method for the case of milk spectra described

above, it can be seen that since the energies of Cs-137 (0.662 MeV) and

K-40 (1.46 HeV) are far apart, there will be no contribution due to

Ce-137 in K-40 region and the above equations simplify to

Pcs + f c s , k ' P k " °1

and

Pce

Pk " C2

where C1 and 0g are the sample counts in the photo-perk regions selected

for Cs-137 and K-40 peaks respectively. The activities due to Cs-137

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and K-40 can be estimated by multiplying P and P. by their total

energy peak efficiencies determined from their standard sources.

Factors f. and photo-peak efficiencies can be accurately determined

from fairly active standard sources of the concerned isotopes. The

geometries of standard sources and the samples should be identical

as otherwise the f factors calculated from source readings wi l l not

be valid for the samples.

The above method i s simple and does not need computers but it

i s applicable only for aamples containing 2-4 isotopes with well

separated gamma peaks. It also requires that the successive highest

energies contain no counts from lower energies either due to overlap

or due to secondary energies* If some of the peaks contain

contribution from more than one isotope, the above method i s not very

useful. For example, i f the sample contains a mixture of aged fission

products, the peak around 660 Kev contains in addition to the 662 Kev

Cs-137 gammas, secondary peaks due to Ru-106 from lh-106 (624 Kev),

Sb-125 (595 Kev) and a small contribution due to Ce-144 from Fr-144

(696 Kev). Therefore, stripping based on the assumption of the peak

being due to only Cs-137 w i l l not give correct results . The methods

described in the following sections take into account the above

complexity.

3.2 Simultaneous Equations Method

Let there be '3' iBotopes in the sample and C(i)tCU\ Cfj)

be the counts in the 'J' photo-peak regions of the various isotopes

determined according to the criterion given earl ier. If F ( 0 , F (2),

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P (k), P (j) ore the photo-peak counts of these isotopes to be

determined, and f (1 , k ) , f (2, k).,,f (k, k\..t ( j , k) are the

compton fractions for isotope F (k) in different regions, the solution

can be found by solving ' j 1 simultaneous equations given by

f (1,1) . P (1) + . . . f . P ( k ) 4 . . . f ( 1 , j ) . P ( j ) - 0 ( i )i i i

i i «

P (1) + . . . f (k,k) . P (k) + . . . f (k, j ) . P Q) = C (k)

f (J,1) . P (1) + ... f (d,k) . P (k) 4 ... f (j, J) . P (j) - C (j)

The above equations can be represented in matrix notation as

f (1,1), f (1,2) f (i, j)

f (2,1) f (2,2) ..... f (2, j)

If (3.0 f (j,2) f (j, j) P (j)

P (2)

C (1)

C (2)

C (i)

or

The solution is represented by-1

-1The i n v e r t e d matrix / " ? _ / i s obtained by means of computer

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when the order i s more than 2. The values of P (j) thus obtained

are multiplied by suitable efficiency factors and decay corrected,

i f required. Table 1 gives a typical set of f ( l , j ) values for

air f i l t er samples containing aged fission products, on 3nx3w Hal (Tl)

crystal for energy regions given in Figure 1a, for three gain settings•

The statist ical errors in the above values can be estimated

as follows:

If the sample has been counted for time TS and the counts

atored in 'J' regions are represented as K1, K2, KJ and if

background i s taken for time TB and the background counts of different

regions are K1', K21, . . . . . . . . K j f respectively, the errors In counts

C (1) , C (2 ) , C ( j ) used in the above formulation are given by,

K1 - K1 ' +c ( 1 ) ± A c X l / _ I s TB

C ( 2 ) ± AC (2)

V

K2 - K2' +TS TB "*

TS2 TB

TS2 TB2

and therefore the variance of the estimated values / P_/ i s obtained

by solving the matrix equation

2 2 2AP (j) « E g ( i , j ) .AC ( i ) f where g ( i , j ) are the elements of the

1 matrix /~?J ~1

estimated and converted to the same units aa F (j) values.

A computer programme for CDC-36OO using the matrix inversion

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method for solving the above equations i s given In Appendix A.

Alternatively, the simultaneous equations obtained above can also

be Bolved by the method of interation. This method i s applicable

here as the criterion for the interation to succeed, namely, that

the large coefficients are along the leading diagonal of the matrix* '

i s satisfied. A Fortran programme using the method of interatlon Is

given in Appendix B.

The final equations obtained after solving the simultaneous

equations for i t s coefficients are given in Table 2 for different

gain settings. Although these equations are not used in their present

form by the computer programme of Appendix A, they are useful In

getting an idea of the stat is t ical and other errors involved as w i l l

be discussed later.

The above method, though suitable for analysis of complex gamna

spectra having a large number of isotopes, uses only the counts stored

in the photo-peak regions. The least squares method described below

i s superior to the above method as i t ut i l izes the counts stored In

a l l the channels and gives better stat ist ical accuracy.

5.3 least Squares Method

If C ( i ) are the counts recorded in the channel fi* of the

sample spectrum, one can write i t as

c (i) - X I x (i,3) . P (j) +Z(i)

where ( i ) i s the random error in the ith channel counts and f ( i , j )

i s a fraction of the photo-peak counts of the Jth isotope in i th channel.

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As before f ( i , ;)) can be calculated fro« the equation f ( i , j ) =

P ( i » j ) A ( j ) where P ( i , j ) i s counts due to isotope J in channel i

and P ( j ) ia the photo-peak counts. The computer programme for

CDC-36OO for calculating these channel fractions i s gLven in Appendix C,

The programme calculates the f ( i ( j ) values for each reading of the

standard source, takes the average of a l l the fractions for a particular

standard and so calculates the standard deviation for each channel

fraction of the standard.

The principle of least squares requires that the sum of the

squares of the random errors Z ( i ) for the individual channels be a

minimum, i . e .

£ z ( i ) - E (c ( i ) - H f ( i , j ) . P ( j ) )i i i

should be a minimum.

Differentiating the above expression partially with respect to

P (j) and equating to zero gives the condition for minimum random

error. We then get f$ ' equations which after simplification can be

expressed in matrix notation as

/V7 . f?J . £vj - Z~P_7 • fcj- - - T

where /"*_/ i s the channel fraction matrix, £fj i s the transpose

of / " F J 7 , /~P_7 snA /~C_7 are column matrices in P (j) and C ( i ) values

respectively.^ the principle of least squares assumee the variance of

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each observation to be the same, which is not true for the gamma

spectra, a diagonal weighting matrix £ W_J of order (n, a) where n

Is the number of channels is introduced in which each diagonal element

is the inverse of the square of the standard deviation of the channel

counts (including background counts) so that

i

TS Ib

Here W (l) i s the ith diagonal element of the weighting matrix, 3 ( l )

i s the sample count rate and B ( i ) is the background count rate In

time TS and TB respectively*

By incorporating the weighting matrix £*_J% the matrix equation

becomes,

- f*J . ZX7 - A 7 - LJ LJand the solution is given by

The P ( i ) values are converted to various activity units aa

described for simultaneous equations. The s ta t i s t ica l errors of the

estimations of various isotopes are obtained by calculating A? ( i )

which are given by the diagonal elements of the inverted matrix aa

follows.

AP (i)2 * i th diagonal elenent of [ 2 X 7 • Z"*7 • L

where R is the goodness of f i t discussed below.

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Thaae AP ( i ) counts can also be converted to the Bame units

as P ( i ) by multiplying them by the activity conversion factors used

for P ( i ) .

The accuracy of the above analysis i s checked, (a) by

reconstructing the sample spectrum using channel fractions f ( i , j ) and

the estimated valueB of P ( i ) , and comparing the reconstructed spectrum

with the recorded spectrum, and, (b) by calculating the value of

"Goodness of Pit" parameter 'R1 defined as

1 ^ (0± - C' )

(n - i) n Var. Ci

where n i s the number of channels, J i s the number of Isotopes, C.i

are the recorded channel counts, C. are the estimated channel counts

and Var . C are given by 1/ff (0 ) . If 'R' i s close to unity, the

analysis i s considered good. Otherwise, i t indicates the presence of

some isotopes not included in the analysis, instrumental drifts etc.

All the above computations are done by the programme given in

Appendix D. The least squares method i s based on 'error minimizing'

principle and i s therefore particularly suitable for weak samples.

The only disadvantage i s that i t needs a computer for data processing.

4. RESULTS AND DISCUSSION

The methods of gamma spectrum analysis described above have been

used with the following three types of analyser systems in use at the

laboratory.

a) A 10-channel analyser having a 3" x 3" Nal (Tl) detector

coupled to Dumont 6363 photomultiplier

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(b) A 100-channel analyser having a 3" x 3" Nal (Tl)

detector (Harahaw integral line assembly)

(c) A 256-channel analyser coupled to a 5" x 4" Sal (Tl)

detector (Harshaw integral line assmbly)

System (a) is being used for the estimation of Cs- (37 and K-40

in milk samples and the gamma spectra are analysed by spectrum stripping

method. System (b) is being used for the analysis of airborne particulate

and rainwater samples for their fission product activities Ce-144, Sb-125»

Ru-106, Cs-137 and Zr-95 and cosmic ray produced isotope Be-7» Tne method

of analysis used are simultaneous equations and least squares. System (c)

is used for analysing soil samples containing natural radioactivity due

to Uranium, Thorium and their daughter products and K-40, and fallout

radioactivity due to Ce-144, Sb-125, Ru-106 and Cs-137. The methods of

analysis used are simultaneous equations and least squares.

Appendix B gives the total efficiency . peak to total ratios

and other factors for the various systems employed.

Figure 3 gives the least square computed and the recorded spectra

of a composite source containing Oe-144, Sb-125, Ru-106, Be-7 and Csr137

as measured in system (c). The f ( i , j ) values were calculated from the

individual measurements of the isotopes of the composite source and the

spectrum analysed has been taken with a l l the isotopes put together,

A goodness of fit value nearly equal to unity can be expect id in

view of the ideal conditions in which f ( i , j ) values were derived for

the measured spectrum. In figure 3(a) analysis was carried out

deliberately omitting Be-7, and accordingly a high value of goodness of

fit of 7.5 was obtained. Here the significant difference between

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caloulated and observed spectra In the region of Be-7 Is clearly seen.

A similar analysis carried out for two air f i l ter samp lea counted

In system (b) are shown In figure 4* Again the large difference in the

region of Be-7 which was emitted in the analysis i s evident. It i s also

clear from Fijure 4 that the routine analysis i s quite precise as lae

computed and measured spectra of the air f i l t e r samples show cloee agreement

when a l l the isotopes present are included in the analysis.

Table 3 gives the photo-peak counts of a fairly active composite

source as unscrambled by the two methods in comparison to the counts from

individual source countings (where no unscrambling procedures are involved).

The data show that there i s not much difference between the two methods aid

the results are correct to within +?0$. Table 4 shows a similar comparison

for air f i l l e r samples. Similar studies have been done with the large

volume sources for soi l studies. The least squares processed results for

a simulated composite source, used in these studies, along with the

individual act ivi t ies are given in Table 5. Comparative results of the

two methods of processing for two typical s o i l samples i s presented in Table 6

and the observed and least squares method computed spectra, averaged for

three channels, i s plotted in Figure 5.

4.1 The effect of analyser gain drift

Since a "drift" in tte gain of system (b) equivalent to a change

in the peak position of about a channel i s not unusual, the magnitude of

this error was investigated. The various f ( i , j ) values were obtained for

three gain settings, v i z . , the normal and two others with Cs-137 photo-peak

maximum one channel above and one channel below the normal. With these

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-16-

three sets of f ( i , j ) values, a large number of samples were analysed.

The results (Table 7) show that far several samples a single channel drift

does not produce more than 15$ error and there i s l i t t l e difference in the

137magnitude of this error from the two methods. However Ce values differ95by as much as 100$ from samples in which Zr i s present in large quantities.

137 95

This i s obviously due to the overlap of the peaks of Ca and Zr

(Figure 1). In the analysis of complex spectra with significant overlap,

'gain1 and 'threshold' shift corrections are important. In studies on the

s o i l sample spectra taken in the 256 channel analyser system i t was found

(Fig.6) that a few isotopes were sensitive to 1 or 2 channel sh i f t s .

The corrections for the instrumental shifts can easily by incorporated(8 9)in the least squares analysis * abd are included in the programme given

in Appendix D.

A CKNOWLDEGHd WIT S

The a u t h o r s a r e t h a n k f u l t o D r . K.G. Vohra , H e a d , A i r M o n i t o r i n g

Section for his interest and encouragement in this work. Thanks are also

due to S/s« K-K. Varraa, D.K. Kapoor and K. Ramanathan for their help.

0 ) G.D. O'Kelley (Ed.), Applications of Computers to Nuclear and

Badiochemistry, Proe. Symp. Gatlinburg, October 1962.

(2) J.R. HeVoe and P.D. IaFleur (Eds.), Modern Trends in Activation

Analys<s, Proc. Conf., Gaitheraburg, Oct. 1968, HBS Special

publication 312 (1969).

(3 ) R^L. Heath, Scintillation Speetrometry - gamma ray apectrua catalogue,Report IDO-16880-1 (1964).

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-17-

4) C. Rangar&;Jan, Computer analysis of complex gamma spectra, in,

Proc. of National Symposium on Radiation Physics, Bombay,

November 1970.

5) J.B. Scarborough, Numerical Mathematical Analysis, Oxford Book

Company, 1964.

6) C.C. Groajean and W. Ljseaert, Table of Absolute Detection

Efficiencies of Cylindrical Scintil lation Gamma-ray detectors,

University of Ghent, Belgium, 1965.

?) tf.c. Mishra and S. Sadaaivan, Nuol. Inst . Meth. 69., 330-334 (1969).

d) E. Sehonfeld, A.H. Kibbey and W. Daviea Jr . , Determinetioa of

Fuclide Concentrations in solutions containing low levels of

radioactivity by Least-Squares resolution of gamma-ray spectra,

Report CSNL-3744 (1965).

9) ?. Quittner and R.E. Wainerdi, Computer valuation of Nal (Tl)

RV& Ge (id.) ganma-ray spectra, Atomic Baergy Review, 8 , No.2,

•561-415 (1970).

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-18-

Table 1

FRACTION OF PUOTOPEAK COUNTS OF VARIOUS ISOTOPES INTHE DIFFERENT PHOTOPEAK REGIONS FOR THE 100 CHANNELSYSTEM FOR THREE GAIN SETTINGS; AIR FILTER AND

PRECIPITATION SAMPLE STUDIES

Photopeak

channelregion

4 - 8

26 - 33

34 - 40

46 - 52

63 - 61

61 - 66

Ce

l.

1.

1.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0,

0.

0,

Fraotlon of144

000

000

000

076

081

079

057

058

057

,075

,067

,057

,064

,070

.077

,034

.034

.004

Sb

0.

0.

0.

1.1.

1.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0,

o,

125

417

388

357-

000

000

000

178

161

216

250

315

430

063

,068

,081

,025

,029

,035

photopeak countsa 10bRu

0.491

0.458

0,337

0.371

0.310

0.263

1.000

1.000

1.000

0,284

0.351

0.400

0.217

0.262

0.193

0.142

0.137

0.123

Ca137

0.169

0.123

0.164

0.209

0.197

0.L21

0.060

0.065

0.075

1.000

1.000

1.000

0.0152

0.092

0.177

0.024

0.025

0.026

InZrNb

0.

0.

0.

0.

0.

o»0.

0.

0.

0.

0.

0.

1.

1.

1.

0,

0,

0,

Isotopes*9595 +

181

151

150

271

213

215

183

182

191

,195

,089

723

,000

,000

,000

,059

,096

,162

Mn

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0,

1.

1.

1,

64

227

179

169

277253

245

336

235

222

120

,115

127

,797

,320

,221

,000

.000

.000

* Calibration137

1st Line C B photopeak maximum in 48th channel

Bnd Line C B photopeak naxlMim in 49th channel137

3rd Line Cs photopeak maximum in 50th ohannel

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- 1 9 -

T a b l e 2

SOLUTION OF SIMULTANEOUS EQUATIONS W S IX COMPONENTSIN TU1£ 1 0 0 - CllANNliL SYSTEM Full ( i , j ) VALUES GIVfcN JH

TA11LE 1

Photopeakcounts ofisotope*

P ( C R 1 4 4 > -

P(Sb125) --:

P(Hu106) =

P(C8137) =

p ( / r95 +

95»Nh* j

P(Mn54) =

Muitip4-ri

1 .054

l.osa

1.041

-0.041

-o .osn

-0.062

-0.034

-0.036

-0.030

-0.050

-0.035

-0.034

-0.033

-0.050

-0.071

-0.027

-0.024

-0.019

+ Calibration

lyinp factors2(1-33

-0.

- ' ) .

-0.

±1-+1,

+1,

-0,

-0,

-0,

-0

-0

-0

-0

•0

+0

40

+0

-0

354

337

280

,133

.125

.164

.172

.146

.211

.207

.281

.433

.012

.009

.045

.014

.005

.ooa

of counts34-40

-0.

- 0 .

-0.

-0,

-0,

-0,

•1,

+1,

+1,

-0

-0

-0

-0

-0

.0

-0

-0

-0

.''.(iO

358

238

.290

.197

,167

.146

, 133

.113

.190

.282

.264

.091

.197

.115

.13 i

.111

.098

in46-52

-0.

-0.

-0.

-0,

-0,

-0,

-0

-0

-0

+1

+ 1

+ 1

-0

-0

-0

-0

-0

•0

OB2

038

095

.201

.184

.227

.015

.022

.004

.067

.076

.245

.033

.074

.196

.014

.011

.011

channel rucolons•>-5 3-til

- 0 .

-0.

+0.

-0,

-0,

-0,

-0,

-0

-0

-0

+0

-0

1

1

1

-0

-0

-0

013

O1H

025

.206

.165

.012

.141

.151

.134

.114

.020

.790

.O7R

,075

.200

.035

.O78

.016

61-66

+0.O003

-0.01O

-0.04S

-0.017

-0.155

-0.207

-0.216

-0.172

-0.160

•0.094

+0.014

+0.176

-0.B14

-0. 2B3

-0.214

+1.076

+1.055

+4.059

1371st Line - C B photopeak maximum In 48th channel

n7n 72nd Line - Cn photopoak maximum In 49th channel4 Of

3rd Line; - Cs photopenk maximum In 50th channel

* The photnpeak counts are equal to the algebraic mira of thegiven fractions multiplied by the counts in the respectiveohannel regions.

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Table 3

PUOTOPJiAK ACTIVITIES OF TWO COMPOSITE SOURCES ANALYSED IN THE 256CHANNEL ANALYSER SYSTEM BY DIFFERENT METHODS

SourceNo.

I

II

Analysis method

Individual sourcecounting

Simultaneous equations

Least squares

Weighted leastsquares

Individual sourcecounting

Simultaneous equations

Least squares

Weighted leastsquares

Ce 1 4 4

992

997(1.00)

904(.9l)

903(.91)

1148

1506(1.31)

1392(1.21)

1408(1.23)

Sb 1 2 5

3240

2725(.

2853(.

2780(.

3392

4081(1

4279(1

4365(1

84)

88)

96)

.20)

.26)

.29)

Photopeak

Be7

2640

2783(1

2680(1

2782(1

-

-

-

counts of

.05)

.02)

.05)

Ru 1 0 6

894

1133(1.27)

1230(1.38)

1171(1.31)

997

1242(1.24)

1337(1.34)

1317(1.32)

Cs 1 3 7

4603

4481(.

4524(.

4550(.

4603

5298(1

5304(1

5179(1

97)

98)

99)

.15)

.15)

.13)

w 54Mn

-

-

-

1750

2067(1

2190(1

2033(1

I

o1

.18)

.25)

.16}

Figures in brackets give the ratio of photopeak counts derived by the method to thatfrom Individual counting

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Table 4

RADIOACTIVITY OF FILTEB SAMPLES ANALYSED IN THE 100-CHANNELSYSTEM BY DIFFEBENT METHODS (ACTIVITIES IN uue/iOOO M )

Saapledate Ce Sb125 Ru106 Cs137 Mn54

S.E. L.S. W.L.S. S.E. L.S. W.L.S. S,E, L.S. VF.L.S. S.E. L.S. W.L.S. S.E. L.S. W.L.S,

1964

FEB.MAR.APfi.

UAY-IUAY-II

AVERAGE

6921110

855

539

480

735

60T1025

77T

530

400

668

520

1012

730

475

333

614

69,2 64.1 67.2

85,,5 85.4 76.1

94,0 111 78.3

58.2 56.5 47.0

44.5 51.2 36.0

70.3 73.6 60.9

318 385 324 75.2 76.0 72.6

445 453 388 119 120 110

334 333 275 111 111 100

222 222 186

197 197 147

303 318 264

66.0 67.5 56.8

60.TB 61.5 50.8

86.5 87.2 78.0

48.0 50.5 47.3

65.8 66.7 60,6

50.5 49.6 44.8

31.6 32.4 27.4 <

27.4 29.1 23.6 ^

44.7 46.7 40.7

S.E. Simultaneous EquationsLS . Least SquaresW.L.S. Weighted Least Squares

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- 2 2 -

T a b l e 5

RESULTS OF LEAST SQUARES METHOD PROCESSING OF SIMULATED SOILSAMPLE SPECTRA OF DIFFERENT COMBINATIONS OF THE ISOTOPES AND

THE CONUliNTRATIONS OF THE ISOTOPES ADDED; 256-UIIANNEL ANALYSERSYSTEM

Isotopes Added

Added Concentrations

K * CB

K + U

U 4- CB

K 4- U 4- CB

K 4- U 4- CB + Ru

K 4- U 4- Cs 4 Ce

K + 11 + Cs + Sb

K 4- U 4- Th 4- Cs

K 4- U + CB 4- Ru + C«

K+U+Cs+Hu+Sb

K+U+Th+Cs+Ru

K+U+Cs+Ru+Sb+Ce

K+U+Th+Ca4-Ru+Sb

K+U+Th+CB +Ru+Co

K+U+Th+C s+Ru+Sb+C e

K+U+Th+Cs+Ru+Sb+Ce

4-2.63 muc Mn

K(R)982

981

982

982

962

982

982

982

982

982

983

982

983

983

983

995

.5

.95

.27

.28

.86

.61

.28

.47

.90

.65

.02

.91

.01

.30

.30

.44

IsotopeTJ(rag)

83.

83.

63.

83.

83.

83.

83,

83

83

83

83

83

83

83

84

86

5

40

40

53

64

64

,65

,65

.77

.78

.77

.89

.89

.89

.01

.23

valuesTh(m)

4.60

4.58

4.58

4.58

4.58

4.58

4.64

obtainedCs{muc)

50

50

50

60

50

50

50

60

60

50

50

50

50

50

50

52

.6

.62

.62

.62

.62

.62

,62

.62

.62

.62

.61

.62

.62

.61

.61

.65

Ru(rauo)

12.

11.

11.

11.

11.

11.

11.

11.

12.

15.

[)

87

90

92

89

96

96

95

01

14

Sb(muo)

26

26

25

25

25

26

26

.0

.95

.99

.99

.99

.00

.01

Ce(onto)

51.0

50.

50.

61.

51.

61.

57.

68

84

17

42 |

08j

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Table 6

BESULTS OF LEAST SQUARES AND SIMULTANEOUS EQUATIONS METHODS OF DATA PROCESSING FORTWO SOIL SAMPLES FOB DIFFERENT THRESHOLD SHIFTS (SAMPLE SPECTRA SHIFTED BY THE

NUMBER OF CHANNELS INDICATED)

SampleNo.

121 A

20 A

Channelset t ing

Noraal

Normal

+ 2

- 2

+ 2+ 1+ 1 forK,U, Thothersnoraal

Noraal- 1- 2

Processingmethod

L. Square

S. Equn.

-do-

- d o -

LEAsTSQ

uAR

§

K

7.08+0.076.86

+0.106.84

6.74

3 ,,193.052.88

2.932. 852.78

U-238

3.29+0.023.G3

+0.052.88

3.12

0.6180.6430.676

0.0730.7100.760

Th-232

12.49+0.03

12.15+0.0511.19

12.91

2.853.043.15

3.173.223.18

Cs-137

588.94+0.99579.72+1.06507.7

605.3

43.549.354.9

54.759.764.0

Ru-106

52.78+1.5353.42+1.73100.6

31.6

49.028.212.7

12.52.78-1.19

Sb-125

43.22±0.6341.56+0.6744.5

50.8

18.215.714.0

13.612.011.0

Ce-144

48.05+0.9844.80+1.8696.4

9 . 0

36.927.519.6

19.211.75.31

Iuu1

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Table 7

RELATIVE VARIATION OF ACTIVITY MEAbURLD IN TIIE iOO-CHANNEL S.YSTEM Foil DIFFERENTUlUNNEL-fciiLllGY CALIBRATIONS

Method C e 1 "Calibration*48 49 50

Calibration*48 49 50

Cr.l48

R,.106

ibration*49 50

Cs 1 3 T

Calibration*48 49 50

Zr*5 • Kb95

Calibration*48 49 50 4S

„ 54Mn

Calibration*49 SO

A.Simulta-neous

equations 0.96 1.00 1.04 0.85 i.00 1.06 0.99 1.00 0.96 1.13 1.00 1.00 - 0.95 1.00 1.12

B.Simulta-neous

equations 0.97 1.00 1.06 0.84 1.00 1.18 0.99 1.00 0.95 1.14 1.00 0.57 0.87 1.00 1.19 1.05 1.00 0.98

C.Leastsquaresanalysis 1.06 1.00 1.07 0.78 1.00 1.37 0.91 1.00 1.16 0.98 1.00 0.79 - 0.68 1.00 1.09 \

re' • t . _ _ _ _ _ _ _ _ _ _ _ — — — — £.

Values relative to the normal calibration (Cs peak in 49th channel) i45 95

A Based on analysis of 25 spectra of air filter samples with Zr* + NbB Based on analysis of 12 spectra of air filter samples with Zr + Nb

C Based on analysis of 6 spectra of air filter samples without Zr + Nb137* Calibration is indicated by the Cs photopeak maximum channel number

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10

- 2 5 -

CHANNEl NUM6ER40

0.1

Ul

S

so

.01

I"

.01

.001 I 130 40 SO 9060 70 BO

CHANNEL NUMBER

FIGURE ". 1 . GAMMA SPECTRA OF SOURCES MEASURED IN C a ) 7.5 cm»

x 7.5cms Na l (T l ) -100 CHANNEL AND,(b) I2.5cmi * 10 emi

N a l ( T D - 2 5 6 CHANNEL SPECTROMETERS.

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- 2 6 -

UJI -3

» -z

8

zo

in

Ou

1200

1100

1000

900

800

700

600

500

400

300

200

100

1000

900

eoo

700

600

400

300

200

100

Cs-137661 KcV K-40

1.46 McV

CURVEW BACKGROUND

Cs-137661 KcV K-40

1.46 McV

NORMALIZED K-40 SPECTRUM

Cs-137 IN THE SAMPLE

0 2 4 6 8 10 12 14 16 18 20 22 24 26 26 30 32 34 36 38 40

PULSE HEIGHT (ARBITRARY UNIT)

FIGURE: 2 . ANALYSIS OF MILK SAMPLE.

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I I I(a) GOODNESS OF FIT s 7.S

LEGEND

CALCULATED

o MEASURED

Ct>) GOODNESS OF F I T . 1.1

10 30 40 SO 60

CHANNEL NUMBER

TO 80 90 100 no

FIGURE .3. GAMMA SPECTRA OF A COMPOSITE SOURCE MEASURED IN THE 256 CHANNEL

ANALY5ER AND CALCULATED BY LEAST SCLUARES METHOD, ( a ) SOURCE

CONTAINING Ce - 1 4 4 , Sb-125 , Ru - 1 0 6 , Cs -137 AND B « - 7 ANALYSED FOR

THE FIRST FOUR ISOTOPES ONLY . (t>) SAME SOURCE ANALYSED FOR

ALL THE ISOTOPES PRESENT IN THE SOURCE.

120

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- 2 8 -

a

e 1000

300

10,000

Xo

LEGEND

CALCULATED

o MEASURED

) AIR FILTER SAMPLE OF MARCH 67

GOODNESS OF FIT c 23

f\ Cb) AIR FILTER SAMPLE OF MARCH 64

GOODNESS OF FIT .1.1

30 40CHANNEL NUMBER

FIGURED. GAMMA SPECTRA OF AIR FILTER SAMPLES MEASURED IN

THE 100-CHANNEL ANALYSER AND CALCULATED BY LEAST

SQUARES METHOD, (a j SAMPLE CONTAINING C«-144, Sb-125,

Ru-10S,Cs-137, Zr-95*Nb-95 AND Bt-7 ANALYSED FOR

FIRST FIVE ISOTOPES ONLY.(b) SAMPLE CONTAINING C«-

144, Sb-125, Ru-106,Cs-137 A Mn-54 ANALYSED FOR ALL

THE ISOTOPES PRESENT IN THE SAMPLE .

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105

=>ooUJ

3a.in

w*

UJu

10

-

9X 1

, • : " • . « ,

• CCHPUTEO COUNTS

t OBSERVE

• a i *

) COUNTS

' . « Mtr

" l

<X

10 30 60CHANNEL GSOUP

SO SO 70 SO

FIGURE'. 5. OBSERVED AND LEAST SQUARES METHOD COMPUTED C0UNT5 (AVERAGE

OF 3 CHANNELS FOR CHANNEL NOS. 1 0 - 2 5 0 ) FOR A TYPICAL

OOTACAMUND 0 - s " LAYER SAMPLE.

I

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OBSERVED SPECTRUM

+ 2 CHANNEL SHIFT

COMPUTED SPECTRUM

- 2 CHANNEL SHIFT

COMPUTED SPECTRUM

NORMAL COMPUTEDSPECTRUM

40CHANNEL GROUP

FIGURE: 6. OBSERVED AND COMPUTED SAMPLE SPECTRA FOR NORMAL AND

+ 2 CHANNEL THRESHOLD SHIFTS,256 CHANNEL ANALYSER, SOIL

STUDIES .

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-31-

APPluMX A

c PROGRAM FOR ANALYSING GAMMA SPECTHA BY SIMULTANEOUS EQUATIONS

C M^THOn USING MATRIX INVERSIONccC THIS Li5TtNu 15 FROM CECK U3'n ?Q« 5OIL ANALYSISC A(I,j) ARF MATRIX COEFFICIENTS

c cm ARE EFFICIENCY FACTORSC C 1 ( 7 ) = C H E C K REGION FACTORSC F(I)=nECAY FACTORSC (M(I),N(I))=LOWFR AND UPPER CHANNELC MlJSflACKGROUNn CHANNEL COUNTS IN TlC M(l)=SAMpLF COUNTS IN J3 MINUTESc COMPT(UJ»=COHPTON FACTORS FOR SPECTRUM SIMULATIONC SW.Tw ApE SAMPLE ANI) TOTAL WEIGHT IN KGC AA=ARrA FACTOR G*NO OF nAYj FOR DECAY CORRECTIONC Yl»nrLYl sSAMPLF ACTfVlTltS ANU E«HORSC C H E C K , E ( 8 ) ,CHTT SCHECK REGION HESlDuAL-RECoRDED^COMPuTEnc un(i),onz(ijsRECoRDEn AND C OMPUTEU SptcTRA THREE CHANNELcC PLOT SUBROUTINE NOT LISTED HERE

N S O N A (7 ,7 } ,P i7 ,7 ! ,KNT«7 I« K J I P S J I , H ( 8 1 , N ( B J , E l « ) , C i 7 )3 C i i 7 j « F ( 4 > * M 4 ) » | . « f l ) ' L ^ ' » » « ° E L L » t | « X ( 7 ) % t ( 7 ) O E X « 7 D Y T 1 ( 7

, i E L 2 4 « 5 eCOMPT<T»250)«IGR/l.PHU01»50j» DU(801 «nDU*O) ,CT '250 )

UI'^FNSION SAM(B) ,BKG(8JUIMFN5ION K ( ) C T TUTMF.NSlflN

703 X M I j s IUTAH 1 0 , « ( A ( I » J ) i I s l , 7 j » J B l ' 7 M « C « I ) » l s l » 7 )

10 FORMAT (7F10.5>11 F0RMAT(7(10X,7F l< t ,5 i / )« / / )

PRINT 9fl5 2 4 OT 1 F , ,98 FOHMAT |10X»25HlNPUT MATRIX COEFFICIENTS,//)

PRINT ll,((Ad,Jl,Isi,7),J=l,7)PPINT l ? . < C d ) i l = l»T)

12 F0RMAT(2Xi3lHpACT0RS FOR C O N V E R ' I N G CJ»M TO UUC»E 1»(Cni)«I

IS FnKHAT(7FlO,5)PRINT 11, ( C K I I I 1 = 1,7)

d i\t* FORMAT

PRINT 15,(F(I),TS1,4)15 F0RMAT(?X,29HnECAY FACTORS FOR C E » R U , C S . M N » " « 1 ° X » « F 1 5 ,

51 FORMAT U6I5)PRINT 5 l i ( ( H ( l ) i N I ] ) ) ,1=1,8)REAP 70 '» t ( (COMPT(T,J ) ,J= l ,2So>* I a l ,T}

7O<» FORMAT (10F«,6)Un l e 1=1,7DO lf l J s l , 7

P ( I , I ) S l t O

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- 3 2 -

A (CONTINUED)

CALL MATlMVRT(A,P,KHT,T)Pi»IMT 91rP I«"ATHOX.. ' ' f lHl"VFPTEn HATRjx COtRfAn ( ) !U . K i

50 FnKP'AT f 1*»I•»IREAP 5 0 l , S l ' . , T l

501 FOt<MATlAfliF<i,0DO 1? 1=1,0L(H=n

UO ">3 JsK53 LUlsL(!l*KJ|5255 HFAP

56HFAP «?01iS»T3RFAP <15, (SW,TW,AA,G)DD <?/• 1 = 1,4

94 u m s F X f F ( F ( 1 ) » R )U" 5n 1=1,A

)KKK?sNM)L l ( ! ) = 0UO 59 J=KK2,KKK?

59 LI <n=LlU)*KHj)5fi lNUr

UO ISO 1 = 1,ASA;-Hn=t 1 ( I>BKG( I ) =i. ( ! )E ( I > = S A M U > / T 3 - W K G

60 U F . L L ( n s S A M ( l j / TUO 16 I a l , 7X ( ! ) s O , nDO 17 J - 1 , 7

17 X ( n = A ( T , J ) « E ( J ) * X < I )16 Y ( I ) = X ( I ) » C t ! > / S W

i)0 19 1 = 1,7

20 J = l , 7X ( T ) = D F L ( ( I f J

Ut 'LX( l )=SQRTF(UFLX( l jU E L Y ) D E C19UO ?\ 1=1,7Y l ( I | = Y ( I j « A A « T W

21 UELYiUO 22

22 ()C H T T B O . ODO 3061=1 ,7CHTT=CMTT+Cl ( I ) «X (nCHEK=F(A)-CHTTDO 70S 1=1,?50

705 C T ( I j s ( K l ( I ) - K J t ) « T 3 / T l lDO 706 1=1,7DO 706 J=1C;25O

Page 36: GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION · 2015-03-30 · B.A.R.C-686 0 300 GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION ANALYSIS OF COMPLEX Nal (Tl) GAMMA-SPECTRA FROM MIXTURES

A (CuNTlMIJEU)

70 ' ) C T l I I t J l =X < f I U O ' I P T 1 1 » J ) « T 3ll ' l 7 , )7 1 = 1 U • O

UO

•/07 C T J ( j ) = ( C T ( J ) - C T Z ( J ) )

UOI ) n ( I ) = 0 . 0

UO 710 J=

710

711 u r u » i ) =1 o n . o712 cnriTinur709 J 1 = J j * l

P P I H T 3

PRINT 3«S»«YiMT>«Isl««i) i < Y H l jP 3 f t « ( T W , A A , G , ( n E L Y ? ( I ) , i « » « < » ) • I p t L V l ( j > » J=5 ,7 ) J

r M F F f l Cp n j M T <O r >» ( [ I P ( I I i l s l t f l f l ) * ( l i j l Z l D • l s l « 6 0 )

36 fGO Tp

100 STOPENU

SI!UR()1)TTNFMATINVRT(A,B,KOUNT,N>

?7 X=0 .

UO3J=1.Mt

I F C X 1 | 2 , 3 , 32 X = A l K 1 , . | )

A » I » j ) a A ( ! i J ) - A ( K l i J J « YS B I I , J ) s n ( l , J K

Page 37: GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION · 2015-03-30 · B.A.R.C-686 0 300 GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION ANALYSIS OF COMPLEX Nal (Tl) GAMMA-SPECTRA FROM MIXTURES

ft

A\?

910

| i i

Y-.t i'iu 1

A(II (t.n

MlK li. ?

i r

j rCOJC

' iT

ft (I. I

I ,i i "

r.y• - *

-y( fi'JT(1i4T= 1

= V ' ' .

!,Jf." 1 t %lJ)=A.J)= n

I (K l

\ + l•>*\] - N !

M)

( I , I)-A(K1,J(T ,J)-l»(Kj »J)-.jr

-M)ljHTm>9tlO»9iNUr

L=L + ).

- 3 4 -

A (CONTINULU)

LM.J

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- 3 5 -

cC AMAlYSlr, OF GAMMA 5PECTRA By ST HULTANEOUS EUU*TIONS HETHOD SOLUTIC ON PY ITERATIONC COM is rOMPTON TRACTIONS fROM SOURCE SPECTRAC N=TOTAL NO OF COMPONENTSc COUNTS TS «KG SUBTRACTED SAMPLE COUNT RAU IN PEAK BFRIC NITsfjn OF ITERATIONSC t F F ( l ) ARF ACTIVITY CONVERSION FACTORS

UMF C N T ESi ) ,COMMON SOTOPE<8),COM(8tB)

1 FORMAT 115)Z F0RMAT<flF8tM3 FORMAT(AF5)«• FORMATU8,2X,2F10>5 FORMAT UOAB)6 F0RMAT(10? FORMAT<1OXI<MA8,<»X) )8

l,NITRFAD «i,(lSOTOPE«I),IsltNIDO ?U J=1,N

20 RFAH ?,(C0M(JiI>*Ial,N»L

READ ?,(EFF(I),Isi,NJVOL»TDL

21 CONTjNUrREAD 3«(COUMT5(J>iJsltN)Dn ?z Ial,N

Z? SOTOPFIT)=0,UO 23 Ksl.NTTDO 23 Msl,NCALL

23 SOTOPFIM)sCOUNTS«H)-Rl00 Z*t 1 = 1,N

24 SOTOPE (I) sSnTOPt (I) »EXPF JO, 693»THL/HLIFE (I» / [ V O L » ^ (IIIPP1NT 6,SAMPLEiV0L,TDLPRINT 7,«lS0T0PEtI}iI=l»N>PRINT «,(SOT0PE«n,Ial,N)

100 STOPEMU

SUBROUTINE SURRC(M,Ri,N)COMMON SOT0PE(B),C0M<8,»>

00 1010 R l S

RETURNEND

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- 36-

A P P E N D I X C

f>rOr,HAH COMMONcc COMPTON F4CTORS FOP LEAST SUUAHES PROGRAMccC APsBACKGROU*1!1 CHANNEL COUNTS, T»B»KG CouNT TIMEC A=SnuRCp CHANNEL COUNTS. TSSSOURCE CUUNT TiMtC NN Is No OF SOURCE READING,NNI«NNZ, CHANNEI LJMTS,NM TOTAL NO OfC CHAMNFLS A N P ACT IS THE ISOTOPE

C CnHPTTtn=COMPTnN FRACTIONScc

A(2?6>. COM(552O),COMPT(256>»COMpTT<256»»COT<236)S O AP(25?)

23<t RFAP 7*(AB(I)t Isl(252)1 READ ?0,SB.TB

20 FORMAT (AB«F4)PPI^T 770,SB»TB

11 READ ?,MNi,MN2,NM,ACT2 FORr'AT <3X,1I3tAej

1F(F.OF»AO)9<>9«33 CONTIMUF

29 FORMAT <5X«12«X,FBt4)»/J93 PRIMj 4, ACT4 FOHHAT (//^OX.ftCoMPToN FRACTION* FoR*»"»26X»AB,//)

REAn 99,NN99 FORMAT II?)

DO 5,K=1,NMCOMPT(H)=0 S COT(K|«0

3 CPNTiNUF.Kl=l SK^sNM SKJsO

6 REAH 7»(A(I)»l=Kl»K2)READ 2O.S,TS

7 FORMAT(1<»F5)PRIMT 44iN

44 FORMAT (2XPRINT 770.S.TS

770 FORMAT (l0XfA8tFl0»/)PP=ODO P.l=NNl»NN2PP=PP*(A(1)-AB(D»TS/TB)

8 CONTINUE

DO 9,j=l,NM

COM«jj)sO.OCOM(jj)=<A(J)-AB«J)«TS/TB)/PpIF(COH(jj))l«tl9»19

16 COM<jj)a0.019 CONTINUF9 CONTINUE

KKl=KJK+l S KK2BKJK+NMPRINT 10

10 FORMAT!/// )12 F0RMAT(5X«12(X»F8,6))

DO l3*Ksl«NM

COMPT(K)aCOMPT <K)*COM(KT)

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- 3 7 -

APPENDIX C '(CONTINUED)

13 CONTfNUF* !29,|COHpT|lt»tKal,NM»N N ) H l 5 1 5l i j N

1 * GO To 61 * DO lfttJsltNM

COMPTT(J)aCOHPT(J)/NN*l!016 CONTINUE

PRINT 10„ PRINT 1?17 FORMATC///»50X»»AVERAGE»«///

PRINT lj>t(CONPTT(J),Jsl«NH|PUNCH 4?0.(C0HPTT(J},Jsl,NMIFORMATf10F6t6)FORMAT (5Xil2re«*l60 To U

999 STOPEND

Page 41: GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION · 2015-03-30 · B.A.R.C-686 0 300 GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION ANALYSIS OF COMPLEX Nal (Tl) GAMMA-SPECTRA FROM MIXTURES

-38-

APPENDIX D

INPUT PA11AMLTERS TO BE UliAD-IN Full PHOG11AMME

= Blank for reading sources, SAMPLE for analysis

using sources already read-in.

N = Total number of channels used for readlng-in data,

Kl & K2* = First and last channel numbers used in actual

analysis,

MTL a Total number of source spectra to be read-in

for the library of standards.

MB = 0 No print-out of source and background input data,

MR s 1 Print-out of background subtracted source counts,

MB = 2 Print-out of source and associated background

counts.

TH « Channel number for zero energy aa calculated

from source spectra*

EFF (I) = Efficiency factors converting unscrambled counts

to activity for isotope I; can be photo-peak

efficiency or simply activities of sources

depending tin source input data.

NPL(I) & NPU(I) = Lower and upper channel numbers limiting the

photo-peak region of isotope (I) used in

calculating the goodness of fit for each

photo-peak area.

FOR! FnR3 ft FOR3= Respective formats to be given for reading-ln

the source, sample and background oountsv

ISOTBPE (I) • Name of isotope T.

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- 3 9 -

TIME

MHK

MBK (si)

MBX (s-

NSMT

COM (i.

Bl. B2. B3. B4

TTIME*

BKS (I)*

MT

NTL

NLF

APPENDIX 1) (continued)

* Half life of isotope I.

s Time of counting of source or sample.

s Source counts taken as such: For sample,

previous background will be subtracted.

s Background to be read-in and subtracted for

both.

= Only for source, previous background will be

subtracted.

s Number of iterations for smoothening source

or sample counts. NSMT s o No data smoothening.

= Calculated channel fractions from source

spectra, source counts or compton fractions

of isotope Jt in channel I.

s Background spectrum title.

= Time of counting of background.

= Background counts in channel I.

s Number of isotopes used in the analysis of the

set of samples following this card,

s The difference (expressed as percentage)

between successive FIT values for termination

of further spectrum shifting iterations.

» Threshold value of error for rejection of the

isotopes. If the quotient of activity of an

isotope divided by its calculated standard

deviation exceeds NLF, the level of activity

is considered to be insignificant. These

Isotopes are omitted and the spectrum reanalysed,

Page 43: GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION · 2015-03-30 · B.A.R.C-686 0 300 GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION ANALYSIS OF COMPLEX Nal (Tl) GAMMA-SPECTRA FROM MIXTURES

-40-

AHl'ENDIX 1) (continued)

= Maximum number of Iterations allowed

irrespective of NTL value,

= Sequence number of fcsotope I to be called-in

from the library of standards.

S1.S2.S3.S4 = Sample title card,, If SlsTERMNT control

passes to first read statement (C0DE)o

SI s REPEAT, for recalculation of previous

sample spectrum„ Data other than the title

in this card should be repeated with

necessary modifications.

VOL = Constant dividing the activity (volume,

weight etc,,)

TDL = Time period for which decay correction has

to be applied; to be given in the same units

as Z (I).

MBl (=0) = No print out of above unprocessed input sample

and background data.

MBl (si) a Print out of background subtracted measured

and calculated counts.

MH1 (s2) = Print out of the above unprocessed input data*

NBK (si) s Background is taken as a component.

NBK (so) s Background is subtracted.

IZR s Source number for which subroutine ZIRC is

to be called; used with TT only for analysis

of Zr9 from Zr95+ Nb95 composite peak.

IZR gives the sequence number of Zr in the

library of standards.

Page 44: GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION · 2015-03-30 · B.A.R.C-686 0 300 GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION ANALYSIS OF COMPLEX Nal (Tl) GAMMA-SPECTRA FROM MIXTURES

-41-

APPENPIX P (continued)

TT * Time since formation of Zr95f In same units

as Z (I); used In the subroutine ZIRC for

seperating Zr" from the composite peak of

Zr95 % Nb95e TT = Ot subroutine ZIRC la not

called In,

WT B Weight associated with each sample. To be

used in calculating the weighted average of

a sequence of samples (along »ith TN)0

TN (=-l) s Start of calculation of weighted average in

a sequence of samples.

TN (si) s Continue calculation of weighted average.

TN (=2) s Last sample in the sequence.

KG e 1 to 4 for plot-out (linear and semilog)

of calculated and input sample spectra using

subroutine GRAPH.

KN =1,2,3,.. for plot-out of every first, second,

third etc., data points.

MN (I) m i for print-out of matrix, Inverse matrix,

unit matrix, channel-wise weight, goodness

of FIT values etc, for the specific iteration I.

* Specified separately for source and sample.

Page 45: GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION · 2015-03-30 · B.A.R.C-686 0 300 GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION ANALYSIS OF COMPLEX Nal (Tl) GAMMA-SPECTRA FROM MIXTURES

- 4 2 -

APPFNtllX n (C0NT1NUEU)

L5QMTFIT

cC ppORuAM FOR LEA 5 T 5Q|JARF S ANALYSIS or NA1(TU) G A M M A S P E C T R A

ccC OPTIONS AMDcC IF C.iHE ( S | A T F M F M T i o ) =S f lMPLE CONjRoL GOEs TO I l 5C IF r n n E I ? "LANK CONTPOL GOES TO NtXT CARnC N = T O T ' L NliM^EP PF CHAMNFL5C HTL = TnTAL NUMRER o r SOUPCt SPF.CTRA I N U I R R A R YC Hn = l OR 2 FOR SOtlPCf DATA Pr, lNT OUTC ' - ! = THKF.SHOLD CHANNEL.C r n H l . F ° " ^ « F n R 3 ARp F()RMATS F ? P " E A U J N G SOURCF. »SAMPLp A N | I n<S COljNTC EFF=FACjORS TO rOMvFRT COUNTS TO ACTIVITYC Ni>U,;jpL ARE LOWFR ANO UPPtR pF.AK C H A H N E L L I M I T SC ISOTOPF. =HAME " F SHIIDCEC I =HALF L I F F

SPECTRAOF SOtlRCF OR SAMPLE COUNTING

C B l » P ? , t n i P < ( ApE HACKGROUNI' T j T L tC TTIMF = TIMF. OF BKS COUNTINGc KI,K? ARE LHWFR Ann JPPER CHANNELS FQH CALCULATIONSC Mi= NuMnER nF SOUPCFSUSED F^R ANALYSJS FROM L J B H A R Y OF M T U SOURCESc N5=SFOUFNCE NO OF ISOTOPES USF.U IN THt PARTICULAR ANALYSISCC 51152,53.54 ARE SAMPLE TITLESc I F SI=TFRMNT CONTROL GOES TO IOcC VOL=wF.lGHT OR VOLUME OF SAMPLFC TDL= pAnioACTlVE DECAY COHRECTlON TlMtC IZR FOR ZR9^ ANALY SIS ONLY AND IS SEQUENCF NO OF ZR95 IN LlB*APYc TT FOR 7R95 ANALYSIS ONLy ANii Is TIME SINCE JR95 FORMAylON ORC SEPARATION

Cc MPK=I FOR BKS READING AND SURTRACTIONC NSMT FOR SMOOTHEM1NG NsMT TIMESC N T L = n T DlFFERNcE(PERCENT) FOR TERMINATING SPECTRAL SHIFTINGC TIONsc NLF=LOWER LIMIT OF ACTIVITY IN UNITS OF S.D, FOR REJECTION OFC ISOTOPES FROM ANALYSIScC IJK= MAXIMUM NO OF ITERATIONS FOR SPECTRAL SHIFTC MR1=1 OR 2 FOR PRINT OUT OF DATAc NRK=1 FOR ANALYSIS WITH B*G AS COMPONENTcC WT=WF_iGHT FHR CALCULATE THE * V R A G E Op A SERIES Op SAMPLESc TN=-i FOR FIRST SAMPLE OF T"E AyRAGlNG SERIESC TM=1 AVERAGING CONTINUESC TNs2 LAST SAMPLE FOR AVERAGINGCC MNJi,-! roR PRINT OUT OF ALL CALCULATED VALUES FOR ITM ITERATIONc PLOT ROUTINE KG=i FOR Y LINEAR KG=2 FOR y *ND z LINEARc KG=3 FOR Y LOGRITHMIC KG=* FOR Y AND Z LOGARITHMICC KM FOR PLOTTING EVEHY KN POINTS

Page 46: GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION · 2015-03-30 · B.A.R.C-686 0 300 GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION ANALYSIS OF COMPLEX Nal (Tl) GAMMA-SPECTRA FROM MIXTURES

- 4 3 -

D (CONTINUED)

cC Si =Pi «[ ft T I rM SfTPFAT A f J * L Y S ! sC TT iLwnL , T i i : r ApF noT C n * N ^ E n FOB R E P E » T ANALYSISC NpK,i iSMT C T r . , A»T cHAN^En F Q R REPF.AT ANALYSISC

,CTS # 2 6 ° ) , D I F F

j i O l x o R i O « ; O > « E F ( 1 o l , t , , , O ) ,l N P L ' j f l ) ' ! J p U U O ) i F ( l O ) » R N l « i n ) » t R l « 1 0 | t

, (C0ntZ=6HTtRiNT) TCOM'^OM M N , i r K , X ocnM""nM K I K ? 9

3 FnRMAT«nEl3)1 2

5 FORMAT MA*)- 136 FORf'ATCSI^iOIZ) i^1 Fnnf'AT<iAAi A6»Fl0 ,2F5,4 j l? i2 ,F 'nF6«F<»'10i l ) 158 F rWATU6r5 ) 1 69 Fr>«MAT<-,AR,A6,F6) 17

12 FPi^ATlSSXiOTHKESHOLn =tt«F3«2X«»CHANNfcLS*t/) 1613 FnHMAT(?Ui^(AS,6X>J ^H FOPHATCtSX.oVOLUHEsotFB'^X^ntCAr TjME=»»F5»/) 2015 F0RM/lT{V»x«flFl/«15J 2116 FnRMAT(/,ft0X,»SnuPCF DATA«,/,^5x,"COUNTS TO ACTIylTY CONVERSION FA 22

ICTOR.so,/) 2319 F0RMAT(l'«X,T3,2X,fl( lx.E12t5») Zh17 FOHHAj (/uSSXioCn'ipTON FP ACTInNS»»/« l2< <«CRtN0*««6x«B(A6«5X) j Zb20 Fn«'AAT(F6,45 26

21 F0HHAT(49Xi«SAMPLF=e,3Afl,A65 2 7

22 FORMAT! / . 5 *X , "INPUT nATA*»»/j 2023 FORMAT U5Xt*MFASURED SAMPLE COUNTS IN»,F6»ZX, I IHIN\JTES( I«/) 2924 FfWATUXtHFfl . l ) 3025 F0H'<AT(/,4bX,3AR»A6t»lN*'Fin,l»lXi*HiNUTES»,/J 3!26 FOKMATUXtll tlX,ElO,3)) 32Z7 F0RMAT(6X«in<Fl l .3 ) ) ' 3329 F0RMATUflX,T2,lX,»ITERATIUNS-C0MPUTED yALUES«» 3^32 FORMAT(35x»nD!FFERENCE BETWEEN MEASURED AND CALCyLATED SAHPLE CftyN 3 >

I T S I N U N I T S OF S . n . « , / > 3633 FOPMAT(5oX»«GOnt!NE55 OF H T (TOTAL ) = o , F 8 , 2 J 373A FO«ViATUbX»»UNScRAMBLEn COUNTS ANN P E R CENT E"RoR°»' '»6X f H <2XtA* 36

1.1X1) 3935 F O R M A T < 6 X , 1 U ? X , A $ , 1 X ) ) <tO36 F 0 R M A T 1 6 2 X » » M A T R I X « , / J <»137 F0RMAT(58Xi*INVFRSt38 F 0 R M A T < < 5 9 X » « U N I39 F0RMAT«/,ft2X,»B(J)»,/J 4*»*tO FORMAT ( 5 1 X I » C A L C U L A T E D SAMPLE C0UNTS»»/» "5<*1 FORMAT(45Xi«8ACK6ROUND SUTBRACTEO SAMPLE COUNTS*,/> 4642 FORMAT!/,55x,#CnM(MTl*2»X)«»/> *\U3 FoRrfAT(31X,»CHANNELWlSE WEIGHTS USED F()R C A L C U L A T 1 0 N OF T H E INpUT -«6

? MATRIX*,/) ^c

^ ^ FORMAT i /.TOX,«CHANNELWISE WEIGHTS USED FOR CALCULATION OF GOO"NFS 50

IS OF FIT VALUE*,/) -!!

45 FORMAT! /,46X,»CHANNELWl5t GOODNESS OF FIT VM.UEs*,/> 5?^8 FORMAT(4OX.«ACTIVITY(MMC) CORRECTED FOR SAMPLE o«-UME *HD DECAY* 53

54

Page 47: GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION · 2015-03-30 · B.A.R.C-686 0 300 GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION ANALYSIS OF COMPLEX Nal (Tl) GAMMA-SPECTRA FROM MIXTURES

- 4 4 -

APPENDIX D (CONTINUED)

^6 run'-"«| J/^JAfVU'Miin'^tir jf '

100 FORMAT |«55x,»ANAlYSlS PARAMETERS*,/,30X,«NUMBER OF CHANNELS«,l3,21X,«NUMBER 0* ISOTOPES ANALYSEns<M3*/f42X,»ANALVSlS STAPJ5 FROM C 572HANNFL «, I3,1X,»TO CHANNEL » , I 3 , / , 3OX» «L0wER DETECTION LIMIT FOR 564 REJFCTION OF ISOTOPES(NLF) IN UNITS OF StD.s^^/ .^TX. t tMAxIHUM. 59ftNUM^Fp OF ITERATIONS«IJtC)s O , f 3 , / ,38X««FJ T DrFFtRENCE IpE/J CENT) F 60«OR TFRMtNATION OF I T E R A T I O N ! N D L ) O « , I 3 ) 61

110 Ff>RMAT(A8) 6Z121 FORMATJ/.^OX^SOURCFsOiAe^HALf LlFE»*«ElO,3tZX»»TlME OF COUNTINGB 63

1,FA,/J1003 FORMAT(^0X«»GnApH OF INPUT!,) AND CALCULATED!*) SpECTR««) 631004 F"«MAT(.10X,»C-«APH Op GAIN SHipTED XNpUT<i) ANQ CALCULATED«•> SPpCT 66

IRA«) 6766 FORMAT(16I5) 68127 FORMAT(A8.E1Z,3,F5«I2»II) 69500 FORMAT*/) 70555 FORWATUH1) 715«6 FORMAT(?X,10«1X,E11,5) ) 7Z1002 FORMATl.iaX»»0OODNESS OF FITJPHOTOI'EA^ REGlONS)B°,F8,2) 737?3 FORMAT(44X»»SHIFT CORRECTED CHANNEL NUMBER*,/) 7*722 rORMAT(nX»10FlO,2) 7b10 RFAn 110,COPE 76

1F(FOF,60) 220,330 77330 CONTiNUF 7G

IftCoDElEo.CoDElJGO TO 115 79REAn 1,N,K1,K?,MTL,MB ,TH 60READ l, (FFF(I>t 1=1,MTL) 61REAO ftb,(NPLjn»NPUU),I

al»MTL) 6ZREAD 2,FOR1»FOR3 63UO "37i jslcN 8<»

971 DKS«J)=n 85DO «»2l jIsl,MTL 8ARiTAn 127,!snT0PE(JI),Z(JI),TrME,MBK,NSMT 67REAn FOR1,(COM«J,J!)iJsliN) 66IF (MhK) g8?ii82i<5B3 g9

983 REAP g«nl,B?«fl3,B*,TTlME 90READ FOR3,(^KS(J),Jsl,N) 91

982 IF(MH-1)966,986,984 92964 PRINT 1?1, ISOTOPE<JI),Z(JI),TIME 93

PRINT 5n6,(C0MU,JI),Jsl«Nj 94IF(MHK)086,<586,g99 95

999 PRINT Z5,0lifl2,B3,B4tTTIME 96PRINT 5fl6,<mcS(I),Isl,N) 97

986 IF(MnK)986»PB7,988 98986 1)0 877 Jal,N 99

C 0 M < J , J I ) = C 0 M ( J U H / T 1 M E - B K S » J ) / T T I M . E 100lF<C0M«JtJll)969i677,877 101

989 COM(J,JI)=0 102877 CONTINUE 103667 CONTINUF 104

IF(NSMTJ921«921«923 105923 DO 922 JK al»N 1 06922 COUNTS(JK)= COM(JK,JI) 1O7

CALL SMOOT«COUNTS»NSMT> 106DO 921 JKsl.N 1 0 9

COM(JK«J1)«=COUNTS«JK) HO921 CONTINUE HI

PRINT 16 JJZ

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-45-

D (CONTINUED*

PRINT ii.dSOTOPEM) tJsl»MTll 113PRINT 1«5.(EFF(I)»IB1,HTL) 114PRINT 1?, TH U 5IF<HH)6«B,6*6,94 116

94 PRINT lTi(l50T0PE(I)tIsl.MTu 117DO lfl Jal.N 118MMSJ 119PRINT lq,MH,(cOH(J»I)«Isl»MTL) 120

IB CCMTlNUF 1216B8 CONTINUE 122

ISOTOPE (MTL*Us2£^ZZ75l466445?'»B 123DO 4 1= l.MTL 1Z«»

4 Z(UsO.693/?«l> 125115 HEAD 6,Kl tK?,MT,NTl,NLF fIKJ, (N5tn,I*l,MT» 126

REAT1 ?,FOR2,FOR3 12TPRINT 500 128PPINT 100* M»HT«K1«K2*NLF»1KJ»NTL 129

11 PREAli 7"sl,52,S3,S4,vOL,TlME,TUL,MBK,MBlfNBIC,NSMT,IZR,TT,«T,TNf 111lKG.Ku,(MN<I)»Ial»lKJ) 132IF(5i;E(j.ConE?JGO TO 10 133

13<*

51 READ <}»nl,B?»P3»B4»TTlMEREAD F0R3,<«KS(DtlBl,N)FS=TIME/TTlME * F X F F

50 CONTTNUF

54PRINT 2««|CnuNT|I),!al»MJPRINT 25«Bl»B2»n3»R4»TTlMPRINT 24« «BKS(I>«tsl»N >

53 CONTINUFMTl=MTLIF«nnK)750,750*751

751 C0NT1NUF

IS(MP)= MTL+1DO 756 jnl,NCOM«J,MTL*l)sBKS(J)/TTIHEG(J)aO

756 CONTINUEZ(MTL*l»aO * EFF(MTL*l)sX«O/VOt

IKJHPsHT 135FITlsO 13*DO 47 J=1«MP I37

47 15<J1=N5(J> 138PRINT 2 1 « 5 l » S ? « S 3 » S 4 139

TF<SltFQ.CnDE3)G0 TO 53 1<|U

PRINT 2? }*1PRINT 14* VOl'TDl 14ZPRINT 23 .7!ME }«NCL=1 «*READ rOR2,(COUNT(II,ial,M) 145

GO TO »3 . ::!750 CONTINUE 170

IF(NCL)9393»193 "

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- 4 6 -

APPENOIX D (CONT1NUEU)

193 i)O <»? J = 1,N 1 7 l

G(J)=RK.s(J)«Fx 1 7 2

COUNT(J)=CO'INT(J)-B|CSIJ»OTIME/TTIME 173|F<CniJNT(J))91»<»2,92 174

91 COUMT(J)=n 17592 C O N T I N U F 176

NCL=n 17793 CONTINUF !yB

224 C O N T J N U F 179

UO ??(, j = l,M i e u

W T = C O U N T ( J ) * G ( J ) iai1F ( W T - 1 . 0 ) 2 ? 7 « 2 Z 7 . 2 2 / }

227 WT=1.02?8 Wl(J)=1.0/WT ill

226 COUMTS(J)=CnuNT(J) . ngJ F ( N S M T ) 9 ? 5 » 9 2 5 9 2 6 {S

J F ( N S M T ) 9 ? 5 » 9 2 5 I 9 2 6926 CALL SHDOT(COUNTS,N5MT)925 K K 1 = K 1 * 1 $ K K ? = K 2 - 1

U^ tq J=1 ,MP<••» ISTr iPF(J)=lSOTOPEfIS(J)) ,SM

I5Tn|.f(Hp+l)=27?13U562302663R l o lI 5 T O P F ( M P + 2 > = 6 3 3 0 6 0 6 0 6 2 3 0 Z 6 % 3 B {it

lSTnPE(MP*1)s62302fi6360606330B225

UO 7q9 I=KK1tKK2

236 IF(CnijNTS(l-l)-l.0(235,235,237 ,21Z35 DCH=n

GO m 7ga237 CONTINUE

UER= -(COU"TS(U1)-COUNTS(I-1))/2.O798 CONTINUE

C O M I M T l l D E K O i /COM(I,MT1*2)=DEB

799 CONTINUFCOH(K1,MT1+1)=COM(KK1,HT1*1)C O M « l l 2 C l l

l S l P * i , S M T i * iI5(Mp+2j3HTU2M=MP*2DO 81 J = l ,NDO »! I = l , HCOMP(J,I)=Wl(j)»COH(J,IS(I))CONTINUEOMP(J,I

81 CONTINUEICK=IKJ.IJH*DO 60 J=1,HDO fto K = 1,M HIAtJtKIHO " 0DO 60 IaKl,K2 2 Z 1

A«J,K)=A(J,(f)*CoH(I,IS(J))oCoHP«I,K) If!

U(J,K)=fl(J,K) * "60 CONTINUF 2Z4

DO l?0 J=l,M Z Z S

B(JlsO,n Z 2 6

DO 120 l=Kl,K2 z|7

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- 4 7 -

n jCoNTlNUED)

229120 CmjTtNUr 230

CftU. INVFRT<A«M» 231UO 10? J=l iM 2321)0 30? K=liM Z33U U * K ) = n 2341)1 30? 1=1.M 235

302 U(J,KJ=P(J»n«A«ttK>«.U<J«M 236un u n J S I , M 23?KH<J) =0.0 236DO 1/.0 I = l tM 231*R M ( J ) = A | J t n » P I I I * R N « J ) 240

140 COMTIHUF 24iSH=SH-RM(HJ 2125HT=-SH

R (&A=1.0-nN<M-l)/100.0DO 271 J=K1»K2CTSlj)=OUO ? 7 1 I = liH 2*t8

271UO 25 IC=K1»K2 251UIFF<K>=CTSfK)-COUNTS<K» 25Z

Ar,5=AnSF«COI)NTS(K|*G<K)» H53T(K)=niFF(K>/SQRTF(ABSI 25^

25 CONTmUr 255FN=O 256DO th J=K1»K2 257A B F = A * 5 F ( C T 5 U ) ) Z 5 B

WTsAHF+r, (J> 259WUlsl.O/WT 260UlFF(j)-n!FF(j>«DlFF(J)«WlJJ 261

262F P R + D ^ F F ( J >CONTJNUF 263

) 26*D 5S J l , P£R<J>=SORTF(A<J»J>«FlT>«»H)0,0/l'N(JI 266

555 CONTTMUr 267CT=O$FT=O 268

IF(NBK)135»135»136135 MPl=MP

00 To 138136 MP1=HP-1 S FtMP)=O138 DO 1000 Jsl.HPl

FU)=o t JJ=NPU(IS(J)) S KDD 1001 I = JJ»KK HI

1001 FU)=F(j)+D!FF(r) 276( " ;F(JJ=F(J)/lKK-JJ)

1000 CONTtMUfFTP=FT/CTPRINT 2O,1CKMTT=HP+3F « H 2

422 CONTtNUFPRINT 3fiPR1N7 27

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- 4 8 -

A P P F N P I X D (CQNTINUEUI

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- 4 9 -

D

201 MPaNx t FlTl*O

GO To 2?fc 3 f t T

CONTINUE202 3MIF(TT)444*444*449 349

445 DO 4/«6 JsltMP »501F<IS<J )#EQ,1ZR)*4T«4*6 351

446 CONTINUE 353*47 CAUL ZInCITTH.t7Ttp.NUH 353444 CONTINUF 3 5>

UO l«0 Jal,HP 35sRN(Jj=RN<J)/<VOL«TIME«EFFt!SjJM» 356

1B0 RH(J|=HM(J)«EXPF(Zll3(J>)»TDL» 35TPPIMT 5nO 358PPI«T 4fl 359PRINT 3S. ( IST0Pt ( t )» I= l9MP) 360PRINT 26t(RNtJ>«J3liMP) 3fclI N t i Z . l . Z 362

35? IF(TN)7U»712«71Z 3637 U UO 713 Jal»HT 364

E"1(JJ=O 365713 RNKjjsQ 366

NTM=o % WT1=O 367712 DO 704 js l tMP 366

RNl(TS(J))sRNl(IS(J>)«RNIJ)«WT 369704 ERl<IS<J>)aFRl(l3lj)|*(ER«J»*RN(jl»WT»0|01)##2 3 7 O

NTMsNTM+l % WTlaWTl*WT 371lf(TN-ltO>n5l,85x«7l6 37Z

716 DO 717 J=1»MT 373RNl«J)=nNlU)/WTl 374F.R1|JJ=SQRTF(ERHJ))/WT1 375

ERKJ)=FRlU)»100 iO/RNKJl 376IF DIVIDE CHECK 7 l 8 i 7 l 7 377

718 ERUj)B0 378717 CONTlNUr BJ7B

PRINT 870, NTM 379870 F°RMAT</ ,30X««AVERAGE VALOES OF L A 3 T » M X * 1 S » *X«»8A"HtS»^l 380

PRINT 35i (fSOTOPE(lJ,I«l»HT) 38lPRINT 2f>i<RNl(J>iJ=l«MT) 382PRINT 2*« ( f R l ( J ) » J e l i M T ) 383

851 IF(KG)ll«Ut853 384853 PRINT 1003 385

CALL GRAPH«KS,N,KN,COUNT»CTS» 3»7PRINT 1004 386CALL GRAPH(KG,N,KN,COUNTS»CTS> 386GO To 11 389

220 STOP 390ENU 391

SUBROUTINE SHlFY<SH,SHC»GA«CoUNT3tNI 1CCC ROUTiNE FOR GAIN AND THRESHOLD SHIFT CORRECTIONS

CDIMENSION CTS<260>«COUNTS(260>tX<260HHN(10> ?COMMON HN,1CK,X 3

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- 5 0 -

A P P E N M X D (CONTINUEU)

K i ,K? *FIHST=CnUNT«i(l) 5un 2nn J = I « N &z=J IX(J)=Z»r,A*&H«(GA-l,O) 8

200 X(J)=x(J)+SHC »IF<MMI!CK))*05.205I206 10

206 CONTinUF 11205 CONTINUF 12

DO 300 jsitN 13XC=J 14UO 203 J=1«N 15xjc=xr-x(j) 1*IF(XJC) Z0l«202»ZO3 1?

202 CTS(l)=rOuNTS(J)/GA ' ItGO To 300 19

203 CONTIHUF. 20201 CTSU) = <C0UNTSU)-e0UNTS(J-ni/IXU)-X(J-l)) 21

CTS«I)=C0l)NTS«J-l)*CT3«l)»«XC-XIJ-l)) 22CT3(i)3CTS«I)/GA 23

300 CONTINUF 24C T S < l ) = l , 0 29DO ?n4 !=1«M 26

204 COUMTS(I)=CTS(I) 27CnUMTS(l)=F!R5T ZflRETIJHM 29ENU 30

SUBROUTINE 9M00T(C0UNTStNT) I

CC ROUTINE FOR SMOOTHENlNQ THE S^^TROH

cC

UIMF.NSlON CTS(260 ) ,C0UNTS(260 ) tX (260 ) ( MN( l0 ) 2COMM()H MN.ICK.X 3COMHnH K1,K? i,K3=rU2 S K<*=K2-2 5Nn=o b

451 IFINQ>NT)45Z,453,<(53 7

452 CONTINUF B

INUF B

DO t/,5 ia K3,K4 9CTS(i) = (l7.0«CoUNTS«l)*12,0»(CoUNTS(I*U*CoUMT3(l-lM-3tO»(COUNTS« 10lU2)+rOuNTS(I-2)»)/35,0 IIIF(CTS(H)4*7t<H>5»445 12CTS(i,s0

445 CONTINUE uCTS(KH=COUNTS(IC1)$ CTS(Ki*D"COUNTS(RI*IIICTSU2-I»«CO»NTSJK2-Ii 15CTS(K2)sC0UNTS«K2) • l f cDO 4<i& I S R 1 , R 2 | .COUNTS<I)=CTS(I) 11

446 CONTINUE 19N Q = N 1N Q O « 1 Zfl

GO To 4!11 2?453 CONTINUE 99

RETURN ftEND JJ

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-51-

D (CONTINUEU)

7lRC(TDL,TT,ZPJ

ROUTINE FOK ESTIMATING ZR«»S PROM ZR95*NB95 COHPOSITEcc

ZRR=?. l6»( i t0-ExPF(- .009l5«TTM 2ZR=ZR/U.O*7RR) 3RETDHN *ENU 5

StiaRoilTlNE INVERT «6iN) 1CCC ROUTINE FOR DOUBl* PRECISION MATRIX iNyERSIONC ROUTINE FROM ALPHA H ORNL-3975CC

TYPE DOUBLE A,B,C»W,Y 2UIMENSlf5N A ( i o , i o ) t B ( i o ) « C { i 0 ) « L Z l l O I * 6 ( 1 0 * 1 0 l 9

DO *»0 T = 1»N *UO 41 J=1,N 5

A U . j ) s G ( I i J ) 6«1 CONTIIIUF 7«0 CONTl IUF 8

DO 10 J a l . N 910 LZ(J)=J

no ?o I = I » N l i12

Y = A ( l , n 13L=I-1 »*LP=1*1 15IF<N-LP>U,H«l l 16

11 DO 13J5LP»N ITWsAU,Jj i«IF(ABSF(W)-ABSF(Y))13.13tlZ 19

12 K=JY=W 21

13 CONTINUE14 UO 15 J = 1 . N

C(J)=A<J.K) z *A ( J , K ) s A ( J t I I H

A ( J » I J = . C ( J » / Y "2T)

15 B ( J J a A l l . j ) , .A « I » l ) S 1 . 0 D / Y z 9

2?L2(!)sL?(K)LZdfjsJDO 19 K=1«NIF(I-K»16»1

16 DO IB J=1«N

1718 CONTINUE

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- 5 2 -

APPENOIX D (CONTINUED)

19 CniiTiMUT 3920 CnNTiMUE

HO ?nO I:liN HiH r<I-LZ(I)>100,200,l00 <»2

100 K=I*1N l O O J

800 l)D '•art J = K , NIr(!-LZ(J) 1500,600,500 46

600 M=L7(I>LZ(T)=L7(J) 46L7(J)=M 49Un 7nn i = l»n 50C(L)=A(I»L) 51A(I»i )=Atj»L) 52

700 A(J,i )=r(L>500 CONTINUEZOO CONTINUE

DO 42 1=1,N 96DO 03 J=1«N 57&tI.J)=A(liJ> 58

^3 CONTINUE 5942 CONTINUE 60

RETURN 61U 62

ccC ROUTINE TO PLOT CALCULATED ANn OBSERvEp rOuNTS IN SEMILOG ORC LINEAR sCALE ROUTINE TROH JAHPO UCRL-19452

cC

DIMENSION *(260)-Y<260),Z<260)»MN<10) ZACOMMON MH.ICK ,X 2 BCOMMOH K1,K? ZCUATA(jNTAPE=60) ,( IOUTAPS61),(K0UTB60I 3DATA(SCALEL=l."E+4) A

500 0000000/)*),<B=1H J,(O'lH,)•(p»lH*)«(SalHII 5A500 FORHflT</) .H5CPRINT 500 >U

PPINT 500 «EDO 200 Jsl,M -p

200 X(J)=J ,GDO ?01 J=ltK5 KM

201 Z(J)=l,0 «jDO 202 J=K6,M 5J

202 Z(J)=i,0 «YHINsY(l) 1YHAX=Y<1) 2DO 1 1=1,M ,YHIN=AMINKY(1),YHIN) q

1 YMAX=AMAX1(Y(I),YMAX) lnIF(K.EQ.l,OR.K.EQ,3)G0T03 }?DO 2 !=1,M tiYMIN-AMIN1(Z!1»,YHIN) \\

2 YMAXsAMAXHZ(I),YHAX) { |

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- 5 3 -

n (CONTINUE"!

IYMAXil.OC-38)

ir(YHAX;EO.YMlN,YHAXsYHAX*l,I»"(K.r,E.,)AsALOr.ioiYMAX/Y«lN|

7 WRlTEJInUTAn(l003JYMINiYMAX SIon ro., "

8 WP.ITI (1OUTA",1OO'4)YHIN,YMAX „

T I1*un inno I=1IMH,N

11 ? . 1 . ( 7 ( U M ! N l / Y D i «:12 IO=?.+«»1.»!Y«I)-YHlNl/YniF 3?

GOTOi«?13 Al=AMAXl<7(!),YMtM)

ir-sP.+gT.eALOGlnlAl14 A2=A(<AXl<Y(!),YMlN)

. , L 6 A 2 / Y t ) A15 I M r .ro.l,On.K.EO,3»GOT01ftO !S

irCIn.liT.lP*l)GnT0ll9 43. T i H i a O 44

I»- «!o.GT.iP)OPTni30 4eIFUu.LT.IPlGOTOUO nl

100 , l J ,I 2 = " I 44

5051

110 I I = I p _ l 52l?= IO- Ip - l 5313=<»f,-ln . 54WPITC(IniJTAPflOO6)X(i) , (H, ja l« U j , p , IB* js l«I?) «Q« <Bt J»l 11 55

13>V5 .

120 Il=!n-1 5«I?=Tp-Io-l 5q13=o f l-lr 6 0WP!TF ( IniJTAPt]0nf>)X(I>,(p.J=i , I l ) ,O,(H«Jslt l2>iP,(B«Jsl«l3>tY(!)« 61

XZII) (,?ooTninnn 63

130 1 1 = I P - 1 6 *I2 6S

6f>6T

140 l l = T n - l 6ft12="f.-If« 6<»

T 70717?

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-54-

APPENDIX 0 (CONTINUED)

T3

&OTO1000 T5160 Il»lo-1 Tft

l?a«)6-n 77WRITE (IOUTAP, 10061 X (II, (BtJ'it I D«Of (8,^1,12)1 Y{!) 70

1000 CONTiNUr 79HBITElIOUTAP.10051 (SiJal^Z* 00RETURN 61

1001 FORHATMX. 9HX *4**£l3,5i 27n»YHjN LlNE«R 5CAl£ ,36X, 62X 5HVMAXa,Cl3,5, <»H V) 63

1008 FoRHAT^X, JHX t4X«El3,S« 47H« HlN LINEAR SCALE V • V 6*X * z I «12H • a MATCHi<iXi 5H MAX=,E13;=,, U H Y 85

1303 FORMAT(^X. 5HX ,ftX,El3i5i Z7H«"HJN LOOARJTHHIC 5ACLCt36X% 6*X 5HYHAX,,El3f5, 4H Yl 68

1004 P0RHAT1.1X. 5HX «<»X,E13,5, *'H HIN L°GARITHHIC SCAUE • Y 89X • s Z «12H • • NATCH'**' 5H MAX«,E13,3, 1*H Y ¥0X 7) 91

1005 F0BMAT«l«.XO2Alj 9?1OO FORMflT(lX,tlO,3»2H t96Al«2E10<3> 9«

ENU 94

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Table E.l»

PHOTOPEAK CHANNEL LIMITS AND MINIMUM DETECTAULE LEVELS OF THE MEASURED ISOTOPESIN TWO GAMMA SPECTROMETER SYSTEMS; AIR FILTER AND PRECIPITATION SAMPLE STUDIES

7.5 x T.5 eras Nal (Tl) - 100 channel analyser 12.5 x 10 cms NaS (Tl) - 256 channel analyserIsotope Photbpeak Area of Background Minimum4

channel photopeak (cpm) detectablelimits scanned level

fl (uuo)

Photopeak Area ofchannel photopeaklimits scanned

Background(cpm)

22.3

26.1

20.8

18.1

12.1

9.3

Minimum*detectablelevel(uuc)

7.0

2.6

7.3

5.2

1.1

1.1

Ce

Sb

144

125

Ru106

137CB

Zr95+Nb

95

Mn54

4-8

26-33

31-36

34-40

46-52

53-61

61-66

92

75

89

87

65

86

78

19.5

13.8

9.9

10.9

6.9

7.3

4.5

5.2

3.2

7.6

5.0

1.5

1.3

1.2

15-19

57-68

66-75

72-80

95-105

110-120

Bl

80

82

85

76

77

IenenI

*For 1000 minutes background oount taking into aocount gamma abundance

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Table E.2

PUOTOPEAK. EFFICIENCIES W VARIOUS ISOTOPES FOR DIFFERENT SAHPLE GEOMETRIES; AIttFIL'fliR AND PRECIPITATION SAMPLE STUDIES

FacTors for converting ciim in photopeak region scanned to u u c activity*I 8 o t o e 7.5 x 7.5 cms Nal(Tl) - 100 channel analyser 12.5x10 cms Nal(Ti) - 256 channel analyser

2.5 cms diam. 5 cms diam. Daily Monthly 2.5 cms diam.perspex disc, perspex pressed pressed perBpex disc,

disc. filter filter

15.7

5.5I

16.9 gI

12.8

3.0

3.7

2.4

•Factors include gamma abundances.

Ce 1 4 4

s*125

Be 7

Ru 1 0 6

C s 1 3 7

zr 9 5+ m, 9 5

Mn54

12.3

9 . 0

25.6

16.0

5 . 5

5 . 0

5 . 8

13.9

10.2

29.0

18.1

6 . 2

5 .7

6 . 6

14.4

10.5

29.9

18.7

6 . 4

5 . 9

6 . 8

15.1

11.1

31.4

19.7

6 .7

6 . 2

7 . 2

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Table E.3

ACTIVITY CONVERSION FACTORS AND MINIMUM DKTECTAULE LEVELS FOR TUP-BA.T CONTAINERS;5"x4" Nal(Tl) - 256 CHANNEL ANALYSER - SOIL STUDIES

Isotope Channel Energy regionregion

Minimum Detectable LevelConcentration percpra in the region Total sample Per gr&m of soil sample

act ivity

jrium-144i

-imony-125

Ruthenium-106

Ceaium-137

Manganese-54

Thorium-232

Uranlura-238

Potassium

14 -

56 -

69 -

94 -

122-

134-

160-

216-

20

67

81

105

13S

157

190

235

0.115 -

0.389 -

0.470-

0.630 -

0.810 -

0.385 -

1.050 -

1.400 -

0.150

0.456

0.550

0.700

0.880

1.030

1.240

1.520

8.14

'J.38

28.12

8.24

7.50

0.048

0.034

0.154

uuc

uuo

uuc

uuc

uuc

•B

ng

g

8.9 uuc

8.9 uuc

26.4 uut

5.6 uuc

4.1 uuc

35.1 ug

25.0 ug

98.6 ng

—34.45 x 10 uuc

—34.45 x 10 uuc-21.32 x 10 uuc

—32.8 x 10 uuc

Q

2.1 x 10" uuc

1.75 x 10"2 ug

1.25 x 10"2 ug4.93 x 10" 2

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- S B -

• I I i ! • =;

• i l ' . i ; ' :T ••, -;—-'••-• —4-r-'

\ A i i r r j r U i m iiiiiiiiii.i.•:.:•;•• ^ &M L " H ! i jTTf f i i ^ i i i l i .liwiliJifeMjl!r f, l b l 4 i;tiIa^ILi ;l!lii:;i!31ii|ili

FIGURE . E l THEORETICAL TOTAL EFFICIENCIES FOR POINT SOURCE ON AXIS 2 1 / Z D I A 2 Vg THICKN a l C T | ; CRYSTAL. ( R E F . 6 )

E - 5 0 4 4 - G - 2 1 6 3

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- S 9 -

FIGURE E 2 . THEORETICAL TOTAL EFFICIENCIES FOR POINT SOURCE ON AXIS 3 OIA 3 THICK

N a l C T | ) CRYSTAL . ( REF . S )E-S044-C-Z164

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- 6 0 -

r^-4--~Li:_..;......;:...,.:.iT.i

FIGURE:E3 THEORETICAL TOTAL EFFICIENCIES FOR POINT SOURCE ON AXIS s"r»IA 4"THiCK N a l ( T OCRYSTAL. CREF.6)

E-5044-G-1138

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- 6 1 -

1.0

ENERGY CMcV)

FIGURE :E4. PEAK/TOTAL RATIOS FOR A 2*D!A.x 2*THICK N a l CT l )

CRYSTAL. SOURCE DISTANCE! 10cmi, POINT SOURCE

10.0

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- 6 2 -

1.0

1.0

ENERGY (MeV)

FIGURE.E5. PEAK TOTAL RATIOS FOR A 2.5*D1A. x 2.5*THICK

N a l ( T l ) CRYSTAL. SOURCE DISTANCE 1 10cmi,

POINT SOURCE.

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- 6 3 -

s

I

1.0

ENERGY CM<V)

FIGURE:E6. PEAU/TOTAL RATIOS FOR A 3*DIA. x 1* THICK N a l

CRYSTAL. SOURCE DISTANCE. lOcmi, POINT SOURCE.

10.0

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- 6 4 -

sOB

ol 1.0

ENERGY CM«V)

10.0

FIGURE.E7. PEAK/TOTAL RATIOS FOR A 3*DIA.x 3*THICK N a l

CRYSTAL. SOURCE DISTANCE! 10cm«, POINT SOURCE.

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- M -

POtNT SOUnCf AT 1Ot.«

TO* HAT CONTAINER

FIGURE: E9 .RESOLUTION or S'OIA 4"THICK Nai (TI) CRYSTALFOR POINT SOURCE AND TOP HAT CONTAINER SOURCES.

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- 6 5 -

CC

0.3

0.2

0.1

0o.i

;

1

'' ii : " : ;!

: 1 • .;,

• I

1.0

ENERGY (McV)10.0

FIGURE-.E8. PEAK/TOTAL RATIOS FOR A 5*DIA.« 4*THICK N o l ( T l )

CRYSTAL. SOURCE DISTANCE! lOcmi, POINT SOURCE.

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- 8 7 -

10

E

to

u

m

10

: \

•• *

1 1 1 1

1 1 1 I

\

i i i i

i t l i

POINT SOURCE AT 1e»

TOP-HAT COKTAIHER

1 l l f

0.5 1.0 i.sEMEKCT CM<«3

FIGURE. E 10.PHOTOPEAK EFFICIENCY OF 5*DIA. 4*THICK

Nal CTl) CRYSTAL FOR POINT SOURCE AND

TOP-HAT CONTAINER SOURCE.