JAERI-Research98-037

JAERI -Resea rch—98-037

JP9808027

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CALCULATIONS OF ACTIVATION AND RADIATION SHIELDINGOF SAMPLES IRRADIATED IN DALAT REACTOR

USING 0RIGEN2 AND QAD-CGGP2 CODES

July 1998

Tran Van HUNG

B * m ? ti ffiff n p/fJapan Atomic Energy Research Institute

(=F319-1195

- (=r319-1195

This report is issued irregularly.

Inquiries about availability of the reports should be addressed to Research Information

Division, Department of Intellectual Resources, Japan Atomic Energy Research Institute,

Tokai-mura, Naka-gun, Ibaraki-ken, 319-1195, Japan.

©Japan Atomic Energy Research Institute, 1998

JAERI-Research 98-037

Calculations of Activation and Radiation Shielding of Samples Irradiated in

Dalat Reactor Using ORIGEN2 and QAD-CGGP2 Codes

Tran Van HUNG*

Center for Neutron Science

Tokai Research Establishment

Japan Atomic Energy Research Institute

Tokai-mura, Naka-gun, Ibaraki-ken

(Received June 17, 1998)

The calculation of the necessary thickness of a lead container for the transportation of the TeC"2

and MoO3 samples, which were irradiated in the Dalat reactor (fuel is U-Al alloy, 36% enrichment235U), is carried out by using ORIGEN2 and QAD-CGGP2 codes. In calculation, cross section library

of PWR type (fuel is 235U-low enriched UO2) is used. For the convenience of comparison with

experimental data, the calculation conditions are similar to the real conditions in the Dalat reactor.

The calculation and experimental results were corresponding well each other in spite of the use of the

cross section library of PWR type. It means that the calculations by using ORIGEN2 and QAD-CGGP2

codes with cross section library of PWR type are acceptable and could be used in calculations of

activity and radiation shielding for different irradiation compositions in the Dalat reactor.

Keywords: Calculation, Activation, Radiation Shielding, Dalat Reactor, ORIGEN2, QAD-CGGP2,

TeO2 Target, MoO3 Target, laq^^Tc

: STA Scientist Exchange Program (Dalat Nuclear Research Institute, VIETNAM)

JAERI-Research 98-037

D A L A

Tran Van HUNG*

. 0RIGEN23- K*5J:tfQAD-CGGP2

ORIGBN23- KfeJ;C5QAD-CGGP23- KMC^fi,

T319-H95

JAERI-Research 98-037

Contents

1. Introduction 1

2. Calculation 1

2.1 Calculation Codes 1

2.2 Calculation Conditions and Parameters 2

3. Calculation Results and Discussions 3

Acknowledgments 8

References 9

Appendix A 10

Appendix B 11

Appendix C 13

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JAERI-Research 98-037

1. Introduction

The Dalat reactor is a pool type research reactor, which was re-constructed from a 250 kWTRIGA-MARKII reactor. During the reconstruction, the nominal reactor power was increased to500 kW. The main purposes of the Dalat reactor are radioisotope production, neutron activationanalysis, research and training. In the radioisotope production, samples are irradiated in theneutron trap with neutron flux about 2x1013neutron cm'V. Two main products in the Dalatreactor with high activity are 13II and 99mTc, which are processed from irradiated TeC>2 and MOO3targets. After the irradiation, the samples are pulled out from the reactor core and placed in a leadcontainer and transported from the reactor room to a hot cell by human power. Thus, the problemof radiation protection for workers should be considered by evaluating the necessary thickness oflead container.

In this report, the calculations of activation strength and the necessary thickness of leadcontainer for the transportation of the irradiated samples, TeC>2 and MOO3, are described.

2. Calculation

2.1 Calculation Codes

Two calculation codes used in this problem are ORIGEN2 [1] and QAD-CGGP2 [2].The ORIGEN2 code is used for calculating the photon characteristic of radio-nuclides producedin the irradiated samples during the reactor operation. It is a versatile point-depletion andradioactive decay computer code for use in simulating nuclear fuel cycles and calculating thenuclear compositions and characteristics of materials contained therein. It represents a revisionand update of the original ORIGEN computer code, which was developed at Oak Ridge NationalLaboratory (ORNL) and distributed worldwide beginning in the early 1970s.

QAD-CGGP2 code is used for evaluation of dose at various points outside the leadcontainer. It is a computer code for the shielding design of reactors, nuclear facilities andradioisotopes, developed in the Japan Atomic Energy Research Institute (JAERI). The QAD-CGGP2 is a point kernel calculation code and is the revised version of QAD-CGGP. In thisversion, the build-up factors for elements calculated with the DLC-15 photon cross section [3] arereplaced by those calculated with the PHOTX photon cross section [4].

JAERI-Research 98-037

2.2 Calculation Conditions and Parameters

(1) Input Data for ORIGEN2 Code

To calculate radioactivity and photon characteristics of irradiation samples by usingORIGEN2, the necessary parameters for input are:

- Weight of 235U in the reactor core- Thermal power of reactor- Weight of elements in target composition- Irradiation timeFor the present study, the above parameters are given in Table 1. Those parameters are

the same as the real conditions in the Dalat reactor. In Appendix A, is shown the workingconfiguration of the reactor core.

Table 1 The parameters for INPUT data of ORIGEN2 code

Parameter

-Weight of 235U (kg)-Thermal power of reactor (kW)-Weight of TeO2 target (g)-Weight of MoO3 target (g)-Weight of Al-container (g)-Irradiation time (h)

Value

3,55001005

100100

The TeC>2 and MOO3 targets are contained in an Al-container and irradiated in the centralchannel of reactor core. Thus, the target compositions are TeC>2+Al and MOO3+AI. The Al-container is a cylinder with size of inner diameter 2 cm, thickness 3 mm and height 20 cm.

In the calculation, the cross sections library for PWR type was used and photon decayparameters are read from the photon decay library for activation products. A sample of inputdeck for ORIGEN2 code is shown in Appendix B.

(2) Input Data for QAD-CGGP2 Code

The output data of the ORIGEN2 calculation about the activity and the photoncharacteristics of radio-nuclides produced from the irradiated compositions of TeC>2+Al andMOO3+AI were used as the input data for QAD-CGGP2 code. The geometrical parameters of thecalculation configuration are shown in Fig 1. With this configuration, QAD-CGGP2 code makes

o

JAERI-Research 98-037

use of the cylindrical coordinate system. The coordinate origin is at the center of the bottom ofthe lead container. Evaluation points are at half height of the lead container and at radial distance0.0, 50 and 100 cm from the lead container surface. A sample of the input deck for QAD-CGGP2code is shown in Appendix C.

Calculation points

Irradiation composition

-d Thickness of lead

Fig.l Lead container and irradiation composition for shielding calculation

3. Calculation Results and Discussions

A lot of information is given by ORIGEN2 output. However, only the information aboutactivation products such as radioactivity, photon emission rate is necessary in the presentproblem. The radioactivity of nuclides was used for the comparison of the calculation results ofORIGEN2 with those calculated by using the basic activation equation. The basic activationequation is as follows:

A(Ci) = m Gact

where, m; weight of target isotope (g), <7act; activation cross section of isotope (barn), 0; thermalneutron flux (n/cm2/s) at irradiation position determined by experiment, No ; Avogadro number(6.023xl023), A; mass number of target isotope, X ; decay constant of radioisotope, T; irradiationtime, t; cooling time.

The purpose of this comparison is to examine the adequacy of the use of the cross sectionfor the PWR type in this case. In Table 2 are shown the activities of radio-nuclides produced inthe activation process of TeC>2+Al and MOO3+AI compositions. The comparisons revealed thatthe results by two methods are corresponding with each other. It indicates that the use of thecross section of PWR type in this problem is acceptable.

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JAERI-Research 98-037

Table 2 The calculated results of the activity of radio-nuclides produced in irradiationcompositions TeO 2+Al and MoO 3 +Al (irradiation time 100 h, cooling time 0 h)

Radio-nuclidesproduced from

TeO2+Al

Al orisin

Te origin

2 7Mg28A1

I23mTe127Te12!Te131Te

131mTe13.j

Total

Activity (Ci)

(1)

0.442.1250.8

0.2437.717.25.900.391.86

116.8

(2)

(*)(*)(*)

0.2840.420.16.530.432.12

Ratio(l)/(2)

0.860.930.860.920.900.88

Radio-nuclidesproduced from

MoOs+Al

Al origin

Mo origin

24Na27Mg28A1

"Mo101Mo""Tcio,T c

Total

Activity (Ci)

0)

0.442.1250.8

1.160.450.970.45

56.4

(2)

(*)(*)(*)

1.330.521.140.48

Ratio(l)/(2)

0.870.870.850.94

(1) Calculation by 0RIGEN2 code.(2) Calculation using basic activation equation with the experimental parameters(*) Not calculated

In Table 2, the total activity of irradiation compositions includes two parts: the activity oftarget materials (TeC>2 and MOO3) and activity of Al container. The energies of gamma raysemitted from the radio-nuclides created in TeC>2 and MOO3 are mainly lower than about 1 MeV,while the energies of gamma rays emitted from radio-nuclides created in Al, are very high,

24*especially, isotope ^Na. The 24Na is created from the reaction 27Al(n,a)24Na (EY=1368 keV,2754 keV, Ti/2=15h). In this Table, all of the values of activity in the column (2) are higher thanone in the column (1). It can be explained that the fuel used in the Dalat reactor is enriched tohigh concentration of 235U (36%) compared with that of PWR. Therefore, the energy spectrum ofthe Dalat reactor is softer, specially, in the neutron trap because of the absence of uranium. Theneutron flux used in ORIGEN2 is obtained by averaging in the all volume of active region, while,in the calculation using the basic activation equation with the experimental parameters, theneutron flux is the value in the neutron trap where it is the maximal value in the active region.These facts will give rise to column (1) values lower than those in column (2).

In the case of the calculation for MOO3+AI composition, 99mTc is one of high activityisotopes. However, 99mTc does not appear in the original decay library of ORIGEN2. In theoriginal decay library, only the transition 99Mo • 99Tc is obtained. In ORIGEN2 code, thematrix exponential technique is used and the transitions with large decay constants areapproximated to "instantaneous" ones; it means that, if the decay constant for B is large (i.e., B isshort-lived) in a decay chain A—* B—• C, the matrix is reformulated as if C were formed from Adirectly. Thus, 99Tc are directly formed from 99Mo, and 99mTc does not appear in ORIGEN2

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JAERI-Research 98-037

output. In the irradiation, 99Tc is produced from 99Mo by two branches. The decay scheme is asfollows:

" MO (T,.=2.6d)

Therefore, in the present case, the decay data of 99mTc was filled up in the decay library.The photon emission rates of the irradiated target composition in the output data of

ORIGEN2 after 2 days cooling time are given in Table 3. The photon emission rate is given foreach energy group as a function of cooling time. That is necessary as the input data of QAD-CGGP2 code. In ORIGEN2 code, the photon energy spectrum from 0 to 10 MeV is divided into18 groups. However, in the present case, the photon energy spectrum is spread in the range from0 to maximum 5 MeV and divided into 16 groups.

Table 3 The calculated results of the photon emission rate for irradiation compositions TeO2+Aland MoOs+Al by ORIGEN2 code

(irradiation time 100 h, cooling time 2 days)

Upper energy of group(MeV)

I.000E-022.500E-023.75OE-O25.750E-028.500E-021.250E-012.250E-013.750E-015.750E-018.5OOE-O11.250E+001.750E+002.250E+002.750E+003.500E+005.000E+00

Total

Photon emission rate forTeO2+Al (photons/s)

1.44E+101.28E+103.32E+092.19E+092.84E+092.17E+091.17E+104.90E+106.60E+095.43E+093.27E+091.39E+081.19E+081.77E+091.21E+061.26E+04

1.16E+11

Photon emission rate forMOO3+AI (photons/s)

8.11E+091.47E+091.18E+091.20E+096.91E+081.87E+091.77E+094.74E+087.62E+073.86E+091.93E+098.90E+037.62E+011.77E+091.21E+061.26E+04

2.44E+10

The calculated dose by irradiation composition TeC>2+Al at different distances is presentedin Table 4 for different thickness of lead container. The calculated doses at 1 m from the leadcontainer for TeO2+Al and MOO3+AI are compared in Table 5 and Fig. 2.

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JAERI-Research 98-037

Table 4 The dose by TeO2+AI calculated at different distancesand for various thickness of lead container

Thickness oflead(cm)

5.06.07.08.09.0

Dose at various distances from lead container0 cm

153960028113262

50 cm

46.426.715.69.15.4

surface (mR/h)100 cm

14.07.904.702.851.71

1 ' r ^ ' I ' ' ' ' I ' ' ' ' I ' ' ' r

-©—DoseofTeO +A1 composition

-13—DoseofMoO +A1 composition

8 9 10Thickness of lead (cm)

Fig. 2 The calculated dose for different thickness of lead container(Distance of 100 cm from the container surface)

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JAERI-Research 98-037

Table 5 The calculated dose at distance of 100 cm from the lead containersurface for TeO2+Al and MoO3+Al compositions

Thickness of leadcontainer (cm)

4.55.06.07.08.09.0

TeC>2+AI composition(mR/h)

22.814.07.904.702.851.71

MOO3+AI composition(mR/h)

17.811.06.754.182.601.61

Table 6 The calculated dose for various energy ranges of gamma rays at distanceof 50 cm from lead container surface, thickness of lead container 5 cm.

Energy range(keV)

<300300 - 375375 - 575575 - 850850 - 12501250 - 17501750 - 22502250 - 27502750 - 35003500 - 5000

Total

TeO2+Al composition(mR/h)

<6.0E-161.11E-032.61E-016.40E+001.27E+11.18E-021.44E-032.63E+012.13E-022.72E-04

46.32

MOO3+AI composition(mR/h)

<1.0E-161.12E-053.15E-O33.23E+007.80E+007.8OE-O59.40E-072.62E+012.12E-022.72E-04

38.10

Al container(mR/h)

<1.0E-184.2E-072.6E-047.0E-047.5E+O02.8E-069.1E-07

2.62E+012.12E-022.72E-04

34.00

Table 5 shows that the doses of TeO2+Al and MOO3+AI compositions are similaras the thickness of lead container increases. If the thickness of lead container isincreased, the radiation dose outside of the lead container is mainly contributed by high-energy gamma-rays. This conclusion is also displayed in Table 6. Thus, the dose by24Na is an important part of the total dose in transporting the irradiation compositions inthe lead container. The 24Na, as above discussed, is created from reaction 27Al(n,a)24Na.The effective cross-section of this reaction depends on the neutron energy spectrum at theirradiation position. Therefore, the difference of energy spectra of the Dalat reactor andPWR should be considered. This problem will be studied in detail after this report.

JAERI-Research 98-037

Table 7 The calculated and experimental doses at various distances fromsurface of lead container with thickness of 5 cm (Dose : mR/h)

Distance fromcontainer(cm)

050100

MOO3+AI compositionCalculation

145138.111.0

Experiment

15404513

Cal/Exp.

0.940.850.85

TeO2+Al compositionCalculation

153946.414.0

Experiment

16205215

Cal/Exp.

0.950.890.93

Cal/Exp. is ratio of the calculated dose to experimental one

The calculated and measured doses are compared in Table 7 for the distances of 0,50 and 100 cm from the surface of lead container. The experimental dose is measuredwith a dosimeter. The results showed that the difference between the calculated andexperimental values is only about 5-15 %. It can be noticed in Table 2 that the activityof radio-nuclides calculated by ORIGEN2 is also about 5 - 15 % less than activitycalculated by using a basic activation equation with experimental parameters.

From Fig. 2 we can determine the necessary thickness of lead container. If wechoose 2.5 mR/h as the acceptable dose level at distance 100 cm from the surface of leadcontainer, the necessary thickness is 8.2 cm.

Thus, from the calculation and experimental studies, we conclude the following:In spite of the use of the cross section library of PWR in the calculation, the

calculation results for activity and dose of irradiation composition of TeO2+Al andMOO3+AI agreed with those by experimental methods within errors of about 5 - 15 %.Therefore, the calculations by ORIGEN2 and QAD-CGGP2 codes with the cross sectionlibrary of the PWR type are acceptable for the activity and dose evaluation in the TeO2and MOO3 irradiation. It will also be able to be applied to the estimations of activity andradiation shielding for different irradiation compositions in the Dalat reactor.

Acknowledgments

The author would like to express thanks to Dr. Hideshi YASUDA, deputy directorof Center for Neutron Science, JEARI, for his valuable recommendations for the workand English proof-reading, Dr. Yukio SAKAMOTO for his continuous supervision andhelp in setting up the research problem. The author is very grateful to Dr. MakotoTESHIGAWARA and Mr. Tadashi NAGAO for their effective assistance.

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JAERI-Research 98-037

References

[1] A. G. Croff., 0RIGEN2 - A Revised and Updated Version of the Oak RidgeIsotope Generation and Depletion Code, ORNL-5621 (1980).

[2] Yukio SAKAMOTO and Shun-ichi TANAKA., QAD-CGGP2 and G33-GP2:Revised Versions of QAD-CGGP2 and G33-GP (Codes with the conversionfactors from exposure to ambient and maximum dose equivalents), JAERI-M 90-110, July 1990.

[3] Oak Ridge National Laboratory Radiation Shielding Information Center DataLibrary Collection DLC-15, "Evaluated Photon Interaction Library ENDF/B Fil23 Format" (1971)

[4] Oak Ridge National Laboratory Radiation Shielding Information Center DataPackage DLC-136,"PHOTX, Photon Interaction Cross section Library".

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JAERI-Research 98-037

Appendix A A plan view of the working configuration of the Dalat reactor core

The Dalat reactor core is cylindrical type, including 100 fuel rods of WWR-M2bundle type, 7 control rods, 4 irradiation channels, graphite and beryllium blocks. Theradius and height of active region are 20.8 cm and 60 cm, respectively. The workingconfiguration of Dalat reactor is shown below.

Graphite

Working configuration of Dalat reactor

Fuel element

Control rod

Irradiation channel

Beryllium block

Beryllium

Neutron trap

- 1 0 -

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1234567891011121314151617

1819202122232425262728293031323334353637383940

Appendix

92 1 1.0-1

-1RDARDABASCUTLIPLPULIBPHOOPTLOPTAOPTFTIT

B A sample of input deck for ORIGEN2 code calculating activity ofTeO2+Al composition

ORIGEN2, VERSION 2.1 (16-10-1997) SAMPLE PROBLEMCALCULATION ACTIVITY OF TELLURIUM100 GRAMS TELLURIUM7 0.001 -1000-10 12-3 -204 -205 -206 93-200-101-102-103 104*8 7 8 7 17*824*824*8COMPOSITIONS OF UNIT AMOUTS OF TELLURIUM ANE

STRUCTION MATERIALSRDAINPMOVHEDBUPIRPIRPIRPIRPIRPIRPIRPIRPIRPIRPIRPBUPMOVSTP20STPRDA

-1= READ FUEL COMPOSITION INCLUDING IMPURITIES (3.5 KG)- 1 1 - 1 - 1 1 1-1 101.01

10.0 0.5 1 2 3 220.0 0.5 2 3 3 050.0 0.5 3 4 3 070.0 0.5 4 5 3 0100.0 0.5 5 6 3 0120.0 0.5 6 7 3 0150.0 0.578 30170.0 0.5 8 9 3 0200.0 0.5 9 10 3 0250.0 0.5 10 11 3 0300.0 0.5 11 12 3 0

12-10 0 1.0292340 0.0 92350 3500 922380 0.0 0 0.0

2-2=READ 100 GRAM TELLURIUM

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JAERI-Research 98-037

41424344454647484950515253545556575859606162636465666768697071727374757677

INPRDAINPMOVADDIRFIRFIRFIRFIRFIRFIRFIRFIRFIRFIRFOUTMOVDECDECDECDECDECDECDECDECDECDECDECOUTOUTEND4040

- 2 1 - 1 - 1 1 1-3=READ 100 GRAM ALUMINIUM- 3 1 - 1 - 1 1 1-2 1 0 1.0-3 1 0 1.010.0-1.0 12 3420.0-1.0 23 3 050.0-1.034 3070.0-1.04 5 30100.0-1.056 30120.0-1.067 3 0150.0-1.07 8 30170.0-1.089 30200.0-1.0 9 10 3 0250.0-1.0 10113 0300.0-1.0 11 12 3 012 1-1012 101.02.0 12 4410.0 2 3 4 020.0344030.0 4 5 4 040.0 5 6 4 050.0 6 7 4 060.0 7 8 4 070.0 8 9 4 080.0 9 10 4 090.0 10114 0100.0 11 12 4 012 1 -1 0-12 1-10

520000 100.0 0 0.0

130000 100.00 0.0

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JAERI-Research 98-037

Appendix C A sample of input data deck for QAD-CGGP2 code calculating doseoutside of lead container

(distance from surface of lead container 50 cm, thickness of lead 5cm)

1 CALCULATION OF GAMMA RAY SHIELDING FOR IRRADIATEDTEO2+AL COMPOSITION

2 10 40 521 1 1 1610 1 1 0 0 0 0 03 l.OE+00 0.0 0.0 0.0 0.0 0.0 0.04 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.91.05 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 8.5 9.06 9.5 10.0 10.5 11.0 11.5 12.0 12.5 13.0 13.5 14.07 14.5 15.0 15.5 16.0 16.5 17.0 17.5 18.0 18.5 19.08 19.5 20.0 20.5 21.0 21.5 22.0 22.5 23.0 23.5 24.09 0.0 0.025323 0.050645 0.075968 0.10129 0.12661 0.15194 0.1772610 0.20258 0.22790 0.25323 0.27855 0.30387 0.32919 0.35452 0.3798411 0.40516 0.43048 0.45581 0.48113 0.50645 0.53177 0.55710 0.5824212 0.60774 0.63306 0.65839 0.68371 0.70903 0.73435 0.75968 0.7858013 0.83411 0.88322 0.93234 0.98145 1.0306 1.0797 1.1288 1.177914 1.2270 1.2761 1.3252 1.3743 1.4235 1.4726 1.5217 1.570815 1.8850 2.1991 2.5133 2.8274 3.141616 GEOMETRDATA17 RCC 1 O.OOOE+00 0.000E+00 5.010E+00 0.000E+00 0.00E+00 2.500E+0118 1.000E+0019 RCC 2 0.000E+00 0.000E+00 5.000E+00 0.000E+00 O.OOOE+00 3.5OOE+O120 2.000E+0021 RCC 3 O.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.000E+0122 7.000E+0023 SPH 4 0.000E+00 0.000E+00 0.000E+01 1.000E+0324 END25 ZON 126 ZON -1 227 ZON -2 328 ZON -3 429 END30 1 2 3 431 11000 2 100032 11 8 52 8233 LEAD EXP 8.73 LEAD34 0.3190 0.2720 0.035 0.0 0.0 11.3436 0.0100 0.0250 0.0375 0.0575 0.0850 0.1250 0.2250 0.3750

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JAERI-Research 98-037

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fcfc'L, 1 eV

r, barnfcj;

N(=l05dyn)

I

9.80665

4.44822

kgf

0.101972

I

0.453592

lbf

0.224809

2.20462

I

lPa-s(N-s/m2)=10P(.f;TX)(g/(cra-s))

lm2/s=104St(X b-:

BE

ft

MPa(=lObar)

I

0.0980665

0.10I325

1.33322XI0"4

6.89476 xlO'3

kgf/cm2

10.1972

I

1.03323

1.35951X10"3

7.03070xlO"2

atm

9.86923

0.967841

I

1.31579X10"3

6.80460XKT2

mmHg(Torr )

7.50062 xlO3

735.559

760

I

51.7149

Ibf/in2(psi)

145.038

14.2233

14.6959

1.93368X102

1

X

+1

ft

ft

J(=107 erg)

1

9.80665

3.6 xlO6

4.18605

1055.06

1.35582

1.60218 xlO"13

kgf-m

0.101972

1

3.67098 xlO5

0.426858

107.586

0.138255

1.63377X10'20

kW-h

2.77778 xlO"7

2.72407x10-°

1

1.16279X10"6

2.93072 xlO-1

3.76616x10-'

4.45050 xlQ-26

cal(frflffi)

0.238889

2.34270

8.59999 xlO5

1

252.042

0.323890

3.82743 xlO"20

Btu

9.47813 xlO"4

9.29487 xlO~3

3412.13

3.96759 xlO-3

1

1.28506 xlO"3

1.51857 xlO"22

ft-lbf

0.737562

7.23301

2.65522x10"

3.08747

778.172

1

1.18171 xlQ-'9

eV

6.24150 xlO18

6.12082 xlO'9

2.24694 x 1025

2.61272 xlO19

6.58515 xlO21

8.46233 xlO18

1

1 cal= 4.18605J (frilSc)

= 4.184J (isft¥)

= 4.1855J (15°C)

= 4.1868J

= 75 kgf-m/s

= 735.499W

Bq

1

3.7xlO'c

Ci

2.70270XW

1

UIt

Gy

1

0.01

rad

100

1

C/kg

1

2.58x10'

R

3876

1

¥itt

Sv

1

0.01

rem

100

1