— —

1A-3954---- — .: ..=.. ./--..‘..: -.. ...—. >-. ,.....

>....-,-, . . . . .. .. . . . ..... .—.%

CIG14 REPORT COLLECTION

a. 3.. -. ., ~EPRoDucT[oN● --—“=.—....~....“.,.-.‘.COPY ‘:___.:.-:i:.’._-::“-::,-.“.. ..-“-- --L--—–-..—-.--~.--,..-.-.:_-—-*”_-%:.----m~.-r.-....-$.-..------=:,------..-–-,.-....--=.;._:_-....—.+—-. — ...’—-. “-“s--——--,-_,_--+_.=..-..—-.........-.-. ...... ...y.—. -..–.. ..-..-,..=.,-.---... ,..-–—-$-.=-,..-..-“..=.—.--..-=..-....-=—..........—+..L:.—.———i-.......-<-:-.—--..,.-.=:.......-—.....___:_.A,-..-::—_....—. ..---=-,.7,..:-..;.. ..........%........ .,.,----LOS AiAli& -;c’i”ENT~;;c” &;j&<Ry”-’” ‘-- “..—. . .....—-”’-, V ._. .----—-.-. >,-=.;._”__,.-=—__~.—---....— ,, —-._-_a_.- -;-.KIf the. .“.-- “--~-~-~~-- ~-----~~~~~~’~~. -. ,+..—--3WL-....a..da---.,,-—“- -..’-.~“;-:;uni”$r;yty’-o f=ca~ffornia ‘ ‘:: y:. ‘=’-~.-.-...”.

.-L-——:-..—>,.,, -...,,~-.-m~-......_—.’_ ~=.–‘“LOS”~“i~”-rn~s ‘e-““~~wz~~x1~“o”-”~d~~-~,‘‘-~~““‘“- ~1-”.“’;~~~~-.. ”“—’.—-.......- ~=:-....-.=-------..-.._.>-..=y..$.-..,::,,,+.:..-....... ....-— -.:--.-+’ ~:.:..-—---- ---;.j>..l,.--7--.%,.*—:.<=”“,-=-in–: :%,,..:........1.. ——., ‘>-.::---J=- .5E+%%3i:~@Q@-::*=: <~#J&&:’-““-----_ ._..—...-’-.... ._.>-.......---.- g-----.,-<..$~:. .-..... -—-----,.>J--V.=..---- ~-..,7 :.=

-,-.

. . .

—- . . . — . ~. — *.: ..-, : : :;--——:- ._ A+ .---—: ;+’--- =_, 7=-4. .—. + -

-—- -.”.—- .>-. . ---- . -:------- . . -, ..<=-:.-. .- . ..-. *. =-.-:-. —- L-. -T -.:,: ., .=::

-. - 1. . -.== -n, .Y– ---- . .:--~– -“ -L-=+.-; .. . -:=.. . ...-*-%-= . -~ A“. ~ ,. ; .>.. .+ y--.~ ,.—. : - . .

-=. - .. —., .._. _,. —- r=_-, ~= =.. —,-.-— +--- ,.----- “

—–

.-. . -. ,— - . ,-A . . . . . .. >— 5 --- .LW...:SLLA?A?- . +---: –--.=.

-- .-:-,’ ,--: <.;-- -

‘___ ,- .,.. ... .

,.

. ----. .-. .-—-. ..T

—————~ - -—___-—...<_J____.. =L-. el - “-’-. ..---,-!—

- .—. -. -S&.=.-~.&!.. . .._ ,... __—- -.—.-.-< . .. ==:-..s -2”=”?- .-2..- :.—---- —,.--J.-L- ~__J

. .._. ——.._—_ ._.—_. < =--+ —=___

. . . . . . =--- —-=. =-=

I—LEGAL NOTICEThis report was prepared se an account of Oovermnent sponsored work. Neither the United

Statea,nor the Commiaaion, nor any person actingon bebaifof the Commission:

A. Makes any warranty or representation,expressed or implied,with respect to the accu-

racy, completeness, or ueefulnem of the information contained in thisreport, or thatthe use

of any information, apparatus, method, or process disclosed in thisreport may not infringe

privatelyowned rights;or

B. Assumes any liabilitieswith respect to the use of, or for damagee resulting from the

use of any information,apparatus, method. or procees disclosed in thiereport.

Aa used in the above. “person actingon behalfof the Commission’) inciudea any em-

ployee or contractor of the Commission, or employee of such contractor, to the extent that

euch employee or contractor of the Commission, or employee of such contractor prepares,

disseminates, or providee acceea to, any information ~suant to his employment or contract

with the Commission, or bie employment with such contracbr.

-.

—.

This reportauthors and

expresses the opinions of the author ordoes not necessarily reflect the opinions

or views of the Los Alamos Scientific Laboratory.

— ---- —.. -.

—

Printed in_ the .United States” “of America. Avtilable fromClearinghouse for Federal Scientific and Technical InformationNational Bureau of Standards, U, S. Department of Commerce

Springfield, Virginia 22151Price: ‘”

.-. ...-Printed Copy $3.00; ‘Micro~che $0.65 -

.. ..--. —. ...—-. . . ..— . .. —-.. .- . . ..- -.. .,

LA-3954UC-80, REACTORTECHNOLOGYTID-4500

LOS ALAMOS SCIENTIFIC LABORATORYof the

University of CaliforniaLOS ALAMOS ● NEW MEXICO

Report

Report

Fission Product

written: November 1967

distributed: October 22. 1968

from

Energy Release and Inventory

239PUFast Fission

by

M. E. BattatDonald J. Dudziak

H. R. Hicks

.

.

s

*

.

FISSION PRODUCT SNERGY RSLEASE AND INVENTORYFROM 239Pu FAST FISSION

by

M, E. Battat, Donald J. Dudziak, and H. R. Hicks

.

ABSTRACT

By uae of currently available experimental and calculated fission productyields from faat fission of 239Pu, the fission product code, FPIC, has been

expanded to include the capability of calculating fission product decay powersfor 239Pu fast flsalon. The revised code, FTIC/U-Pu, is operational on theCDC-6600 computer. Summation calculations of beta, gamma, and total decay powersfrom 235u thermal fission and from 239Pu fast fission were compared for both aninstantaneous burst and infinite irradiation. Shutdown times ranged from 10 to109 ser., and significant (>10%) differencea,occur principally for very shortand very long shutdown times. The decay powers from 235u thermal fission werecompared with previous studies for an instantaneous burst and for infiniteirradiation, and good agreement was found over the applicable shutdown times.calculations of beta, gamma, and total fission product decay powera from 239Pufast fission for a specific irradiation history were then compared with thecorresponding experimental measurements by K. Johnston of AWRR, as well as with235u thermal fission calculations. For gamma and total decay power, the 239Pufast fission calculationsfor beta decay power, the ~35U the~a~ f~saion ca~culations were genera~~y better.

enerslly agreed better with the experiment, whereas

Similar conclusions were drawn from comparisons of instantaneous burst calcula-tions with the corresponding analytical fits derived from the experimental data.

,

.

INTRODUCTION

In evaluating the safety aspects and shielding

requirements for a power reactor, it is necessary

to know the energy release which accompanies the

decay of fission products. For 235U thermal fis-

sion, the large amount of experimental data on

fission yields permits fairly accurate computations

of decay power to be made. Many compilations of

the decay properties of mixed fission products from235

U thermal fission have been published,1

includ–

ing the summation studies of Perkins and Kingz and3

a later revision by Perkins. Perkins’ aummat ion4

study was further updated by Koebberlfng et al.,

who also incorporated their data in an IBM-7090/

7094 computer code, the Lockheed Fission Product

Inventory Code (pPIC). In contrast to235

U thermal

fission, the experimental data on fission product239

yields from Pu fast fission are aparse; hence,239

calculations of decay powera for Pu faat fission

are necesaarlly baaed on the small amount of experi-

mental data. Fission yields versus masa number

have been reported by Burria and Dillons and by

Weaver et al.6

Fission product yields from fast

(=1 MeV) neutron fission of 239Pu have also been7

estimated by Anderson, using the 16 measured

yields published through June 1965. From these 16

yields, together with eix reflected data points,

Anderson obtained estimates of unmeasured masa

chain yields. From these mass chain yielda, and8

using Wolfsberg’s modification of the equal–charge-

displacement hypothesis, Anderson then arrived at

independent and cumulative fission yields, versus

Z and A, for239

Pu fast fission.

CALCULATION OF DECAY POWER FOR239

Pu FAST FISSION

To permit calculation of fiaaion product decay235 239

powers for U thermal and Pu fast fission,

Anderson’s calculated yielda for239

Pu fast fission

were incorporated, as an added input, in the Lock–

heed FPIC code. As originally written, the FPIC

code contained data for 200 nuclides with half-

livea greater than 10 sec and fission yields great-239

er than 0.001%; the Pu data first added to the

FPIC library were for these 200 nuclides.

3

While the plutonium data were being added, some

changes were also made in the FPIC library; a major

‘l’y,whichchange was the addition of the nuclide

was not included in the original library. For the

most part, the remaining changes were to correct

typographical errors and for internal consistency.

The changes made in the FPIC library are de-

tailed in Appendix A. These changes, together withthe 239

Pu fast fission yields, were included in a

new code, FPIC/U-Pu, written for the CDC-6600 com-

puter.

The nuclide decay data and235

U thermal and239

Pu fast fission yields used as input in the

FFIC/U-Pu code are tabulated in Appendix B. Also

included, for completeness, are the body-organ dose

conversion factora as originally specified in the

Lockheed FPIC code. The operating instructions for

the FPIC/U-Pu code are listed in Appendix C.

CQMFARISON OF 235U DECAY POWRR CALCULATIONS WITHPREVIOUS STUDIES

In regard to the235

U thermal fission data,

calculation made with the FPIC/U-Pu code for in-

stantaneous fission (10 f/see for 0.1 aec) and

infinite irradiation (1 f/see for 1020

see) were

compared with results of previous studies. For

instantaneous fission, it was found convenient to3

compare with the summation study of Perkins; for

infinite irradiation, the review of Shure and

Dudziakg was chosen. Results of these comparisons

are ahown in Table 1. In connection with Table 1,

it is important to note the following: (1) the

FF’Ic/tJ-Pu library considers only nuclides with

half-lives greater than 10 see, (2) Perkins’ study

includes only nuclides with half-lives greater than

about 1 rein, and (3) the review of Shure and Dud-

ziak includes total decay power data for shutdown

times as low as 0.1 sec. Thus, although the fig-

ures based on Perkins’ summation study and the FF~C/

U-PU code are not quite valid for shutdown times

below several hundred seconds, they have been in-

cluded to indicate the deviation to be expected for

short shutdown times. For shutdown times greater

than 103 sec and instantaneous fission, the beta

and total decay powers calculated from FPIC/U-Pu

are within _&i% of Perkins’ data, with the gamma

power deviating by about ~12%. For shutdown times

greater than 103 sec and infinite irradiation, the

ratio of FPIC/U-Pu to Shure and Dudziak’s valuea

varies between 0.95 and 1.02 for beta and total

power and between 0.95 and 1.08 for the gamma power.

CALCULATED DECAY POWRRS -235

U THERMAL AND239PU

FAST FISSION

It is of intereat to compare results obtained235 239PU

wtth the FPIC/U-Pu code for U thermal and

fast fission decay powers. b before, two caaea

were considered--inatantaneous fission and infinite

irradiation. Results of these calculations are

displayed in Tablea 2 and 3, respectively. The239PU:235

ratio of U total decay powers variea in a

complicated manner and rangea from about 0.67 to

1.5 for shutdown times shown in Tables 2 and 3.

For shutdown times between 102 aec and one year,

the ratio of total decay power (Pu:U) for instan-

taneous fission varies between 0.78 and 1.3; for

infinite irradiation, this ratio rangea from 0.89

to 1.0. The detailed behavior of this ratio for

beta, gamma, and total decay powers can be inferred

from the calculated valuea ahown in Tablea 2 and

3. Although the239

Pu decay powers given in Tables

2 and 3 are based on a aemitheoretical approach,

it is reasonable to suggest that the ratios shown

in these tables give some indication of the effect235

of using U thermal fission product data for fis-

sion products from plutonium-fueled fast reactors.

COMPARISON OF SUMMATION STUDIES WITH EXPERIMENT

Calorimetric experiments of fission product239

energy releaae after faat fission of Pu have

been performed by Johnston.10

In these experiments,

Johnston exposed four sinilar plutonium samples in

the Dounreay Fast Reactor, the irradiations being

intermittent over perioda as long as 125 days.

Total exposurea at power ranged up to 37 daya. He

obtained data for shutdown times from 45 to 125

days,11

with separate beta and gamma contributions

being deduced from the measurements. The beta and

gamma contributions were separated by the use of

thin-walled capsulea, a removable gasrsa abaorber

in the calorimeter, and suitable corrections for239

gamma energy escape, Pu alpha heating, etc. Hia

samples numbered 1 and 2 were exposed near the cen-

ter of the core, and samples numbered 3 and 4 near

the core edge. After two beta and gamma decay

power measurements at 45 and 66 days, sample 1 waa

.

0

4

.

.

CALCULATED 235UCOMPARED WITH

TABLE 1

THERMAL FISSION DECAY POWERSPREVIOUS SUMMATION STUDIES

1.1-235 THERNQL FISS. FPIC=FPICAJ-PU. REF Q=PERKINS. REF B=SHURE FIND DUDZ19K

T5 BETR--MEV/FISS FPIC/ GQMM9-MEU/FISS FPIC/ TOTrlL-MEV/FISS FPIC/0.5EC) REF 9-B FPIC REF REF Q-B FPIC REF REF Q-B FPIC REF

lE+I

1E+2

2E+~

4E+.2

I E+3

2E+3

4E+3

1E+4

2E+4

4E+4

7E+4

I E+s

2E+5

4E+5

I E+6

2E+6

4E+I:,

1E+7

2’E+7

4E+7

lE+S

INSINFINSI NFINSI NFINSI NF

4.70E+O03.47E-033.05E+OQ2.02E-C132.58E+O09.88E-042.14E+o0

2.

::2.2.2.

)

18E-0266E+O013E-0385E+O066E-0348E+O018E-0313E+O0

.781.48

.931.32

.961.191.00

5.3oE+m3.49E-033.53E+O02.30E-033.00E+OO1.21E-032.54E+O0

7.36E-033.71E+O04.93E-033.16E+o02.94E-032.77E+o01.39E-032.37E+O0

INS 4.20E-04 4.31E-04 1.03 4.43E-04 4.47E-04INF 1.72E+O0 1.72E+O0 1.00 2.OIE+OO 1.91E+O0INS 2.02E-04 2.03E-04 1.00 2.24E-04 2.12E-04INF 1.42E+O0 1.44E+O0 1.01 1.70E+O0 1.62E+O0INS 8.41E-05 8.64E-05 1.03 1.08E-04 9;89E-05INF 1.18E+O0 1.18E+@0 1.00 1.40E+O0 1.33E+O0INS 2.57E-05 2.68E-05 1.04 3.62E-05 3.16E-05INF 9.20E-01 8.99E-01 .98 1.03E+O0 9.99E-01INS 1.12E-05 1.15E-05 1.03 1.28E-05 1011E-05INF 7,58E-01 7.26E-01 .96 8.12E-01 8.13E-01INS 4.84E-OG 4,78E-06 .99 4.82E-06 4.34E-oGlNF 6.1OE-O1 5.80E-01 .95 6.60E-01 6.79E-01INS 2.18E-06 2.llE-06 .97 2.35E-06 2.!9E-06INF 5.1OE-O1 4.85E-01 .95 5.60E-01 5.87E-01INS 1.24E-06 1.19E-06 .96 1.44E-06 1.39E-06INF 4.53E-01 4.37E-01 .96 5.05E-01 5.35E-01INS 4.OGE-07 3.86E-07 .95 !5.49E-07 5.64E-07INF 3.82E-01 3.70E-01 .97 4.18E-01 4.49E-01INS 1.49E-07 1.41E-07 .95 2.45E-07 2.63E-07INF 3.35E-01 3.25E-01 .97 3.47E-01 3.74E-01INS 5.74E-08 5.47E-08 .95 1.00E-07 1.llE-07INF 2.85E-01 2.75E-01 .96 2.55E-01 2.74E-01INS 2.89E-08 2.79E-08 .97 4.55E-08 5.09E-081NFIr{sI NFIN5Ir{FINSlNFI r{sI NF1){SIt{F

2.44E-011.34E-082.02E-CI14.66E-OFJ1.59E-012.CIIE-091.29E-018.4OE-101.02E-012.OOE-107.85E-02

2.37E-011.32E-081.99E-014.GOE-091.54E-011.98E-091.24E-018.19E-10SJ.92E-021.94E-lo7.44E-02

.97

.99

.99

.99

.97

.99

.96

.97

.97

.97

.95

1.88E-011.77E-081.33E-014.98E-097.90E-021.60E-095.00E-021.96E-103.70E-023.13E-113.25E-02

dissolved for mass spectrometric and radiochemical

analysis to determine the plutonium isotopic compo-

sition and the total number of fissions in the sam–

ple (estimated accuracy, ~3%).

Using the FPIC/U-Pu code, Johnston’s irradia-

tion histories (see Table 1 of Ref. 11) have been

duplicated* by summation calculations with both the239

Pu fast fission and235

U thermal fission lib-

raries. The results for samples 2, 3, and 4 are

shown in Tables 4, 5, and 6 where H6’ ‘Y’ and ‘B+y

*In order to perform calculations duplicating theexperiment, the exact masses of PU02 in each samplemust be known. These data are in Table 5 of Ref.11.

2.00E-011.93E-1381.37E-015.OIE-098.1OE-O21.59E-095.14E-022.OOE-103.85E-1323.36E-113.46E-02

2.91E-02.70 l.COE+Ol 7.37E+O0 .74.41 6.96E-03 1.OIE-02 1.45.90 6.58E+O0 6.OIE+OO .91.28 4.32E-03 5.GOE-03 1.30.92 5.58E+O0 5.25E+O0 .94.15 2.20E-03 2.57E-03 1.17.93 4..01 8..95 3..95 4..95 3..92 1..95 2..87 6..97 1..87 2.

4.8.3.4.3.

;:5.1.2.

50E+O078E-0463E+O015E-0406E+O085E-0451E+O084E-0590E+O026E-05

1.00 1.57E+O0 1.54E+O0.90 9.G6E-G6 9.12E-06

1.03 1.27E+O0 1.26E+O0.93 4.53E-OG 4.30E-06

1.05 1.07E+O0 1.07E+O0.97 2.68E-06 2.58E-06

1.06 9.58E-01 9.72E-011.03 9.55E-07 9.50E-071.07 8.COE-01 8.19E-01!.07 3.94E-07 4.04E-071.08 6.82E-01 6.99E-011.11 1.57E-07 1.66E-071.07 5.40E-01 5.49E-011.12 7.44E-08 7.88E-081.OG1.091.031.011.03

.991.031.021.041.071.06

4.3.3.9.2.3.1.1.

1.

32E-O 111E-0835E-0164E-0938E-0161 E-0979E-0104E-CF339E-O 131E-10

.llE-01

4.37E-013.25E-083.36E-019.61E-092,35E-ol2.57E–091.75E-011 ,I)2E-09

1. I.E,E-131~.~~~-llj

1.O?E-UI

.961.02

.97

.97

.98

.96

.97

.94

.97

.94

.98

.94

.79

.951.00

.961.01

.991.02

.03

.02

.05

.02

are the beta, gamma, and total decay powers, res–

pectively. Johnston estimates his maximum random

errors to be ~5 VW per measurement.

On the basis of these summation studies, it

aPPears that using the239

Pu fast fission yields

generally provides significantly better agreement

of the gamma and total decay powers with Johnston’s

experiment. However, for beta decay power, the235

U thermal fission yields more adequately repre-

sent the experimental results, which are consist-239

ently underestimated by the Pu fast fission

calculations.

5

TABLE 2

CALCULATED 235U THERMAL FISSION AND239PU

FAST FISSION DECAY POWERS FOR INSTANTANEOUS FISSION

TS(SEC> BETFk-tlEU/F-SEC 239/ GFIIIIMIHIEU/F-SEC 239/ TOTFIL-tlEU/F-SEC 239zPU239 U235 235 PU239 U235 235 PU239 U235 235

1.00E+O1 1.35E-02 2.18E-02 .62 6.09E-03 7.36E-03 .83 1.9GE-02 2.131E-02 .671.00E+02 4.32E-03 5.13E-03 .84 3.49E-03 4.93E-03 .71 7.81E-03 1.OIE-02 :;;2.00E+02 2.39E-03 2.66E-03 .90 2.14E-03 2.94E-03 .73 4.53E-03 5.60E-033.00E+02 1.5GE-03 1.67E-03 .93 1.46E-03 1.94E-03 .75 3.02E-03 3.61E-03 .844.00E+02 1.13E-03 1.18E-03 .96 1.09E-03 1.39E-03 .78 2.21E-03 2.57E-03 .861.00E+03 4.22E-04 4.20E-04 1.01 4.25E-04 4.47E-04 .95 8.48E-04 8.67E-04 .982.00E+03 2.OIE-04 2.02E-04 1.00 2.16E-04 2.12E-04 1.02 4.17E-04 4.13E-04 1.013.60E+03 9.51E-05 9.90E-05 .96 1.llE-04 1.12E-04 1.00 2.06E-04 2.llE-04 .984.00E+03 8.21E-05 8.64E-05 .95 9.77E-05 9.89E-05 .99 1.80E-04 1.85E-04 .5I71.00E+04 2.21E-05 2.68E-05 .83 2.77E-05 3.16E-05 .88 4.98E-05 5.84E-05 .852.00E+04 8.78E-06 1.15E-05 .77 9.31E-06 1.llE-05 .84 1.81E-05 2.26E-05 *8134.00E+04 3.73E-06 4.78E-06 .78 3.85E-06 4.34E-06 .89 7.58E-06 9.12E-06 .837.00E+04 1.77E-06 2.llE-06 .84 2.02E-06 2.19E-06 .92 3.79E-06 4.30E-06 .888.64E+04 1.31E-06 1.51E-06 .86 1.56E-06 1.68E-06 .93 2.86E-06 3.19E-06 :;;1.00E+05 1.06E-06 1.19E-06 .88 1.30E-06 1.3’3E-06 .93 2.35E-06 2.58E-062.00E+05 3.73E-07 3.86E-07 .97 5.42E-07 5.64E-07 .96 9.15E-137 9.513E-137 .964.00E+05 1.38E-07 1.41E-07 .98 2.50E-07 2.63E-07 .95 3.88E-07 4.04E-07 .966.05E+05 8.36E-08 8.95E-08 .93 1.66E-07 1.81E-07 .92 2.49E-07 2.70E-07 .921.00E+06 4.79E-08 5.47E-08 .88 9.84E-08 1.llE-07 .88 1.46E-07 1.66E-07 .~~2.00E+06 2.28E-08 2.79E-08 .82 4.42E-08 5.09E-08 .87 6.70E-08 7.88E-OS .852.63E+06 1.69E-08 2.llE-08 .80 3.14E-08 3.58E-08 .88 4.83E-08 5.69E-08 .854.00E+06 1.04E-08 1.32E-08 .79 1.76E-08 1.93E-08 .91 2.80E-08 3.25E-08 :;:1.00E+07 4.05E-09 4.60E-09 .88 4.91E-09 5.OIE-091.58E+07 2.75E-09 2.67E-09 1.03 2.49E-09 2.55E-09

.98 8.97E-09 9.61E-09

.97 5.24E-09 5.22E-09 1.%2.00E+07 2.24E-09 1.98E-09 1.14 1.57E-09 1.59E-09 .99 3.82E-09 3.57E-09 1.073.16E+07 1.49E-09 1.1OE-O9 1.35 5.O5E-10 4.48E-10 1.13 1.%IE-09 1.55E-09 1.2’?4.00E+07 1.18E-09 8.19E-10 1.44 2.7OE-10 2.OOE-10 1.35 1.45E–09 1.02E-05’ 1.421.00E+08 2.89E-10 1.94E-10 1.49 6.17E-11 3.36E-11 1.84 3.51E-10 2.27E-10 1.543.16E+08 2.43E-11 4.68E-11 .52 2.46E-11 2.15E–11 1.14 4.851E-11 6.83E–11 .711.00E+09 1.26E-11 2.65E-11 .48 1.44E-11 1.30E-11 1.11 2.71E-11 3.95E-11 . t;8

In evaluating the significance of the percent

difference between experiment and summation calcu-

lations, ae given in Tablea 4, 5, and 6, the in-

herent errors in the experiment must be considered.

The 95% confidence limits given by Johnston are

~7% for beta, ~10% for gamma, and ~6% for total.

Thus , the percent differences in Table 6 for total

decay power are almoat all within the experimental

error. The disagreement between experiment and the239

Pu fast fission summation study could also be

partially due to ayatematic errora in either the

experiment or in the yields as calculated by Ander-7

son. The yield values also depend upon incident

neutron energy, the dependence being most sensitive

at maas numbers close to and on either side of the

peaks in the mass yield curve. ‘llms, an additional

uncertainty ariaea from the different spectra of

the neutrona inducing fission, between the experi-

ment in the Dounreay Fast Reactor (median fission

energy =0.5 MeV) and the =1 MeV energy used by

Anderson. As can be seen from Tables 7 and 8, for

an instantaneous burst, it is just such isotopes

with a sensitive yield dependence which are domi-

nant contributors to the decay powers at the shut-

down times covered by the experiment. Though it

appears less likely, uncertainties in the total

beta energy release per disintegration could also

be a significant factor in accounting for the dis-

crepancies. Differences between calculation and

experiment could also arise from difficulties in

determining precise ehutdown times for reproduction

of the reactor operating history, although this

error should be quite small.

COMPARISON OF ANALYTICAL FITS WITH CALCULATIONS:INSTANTANEOUS BURST

From hia experimental results, Johnston derived

analytical fits to the data, in the usual form,

.

.

H(t) = ANu f[t-x - (t +T)-x], (1)

6

TABLE 3

CALCULATED 235U THERNAL FISSION AND 239puFISSION DECAY POWERS FOR INFINITE IRRADIATIONFAST

1“S(SEC) BETI1--tlEU/FISS 239/ gR##IEV/FISSPU239 U23S 235 U235

239/235

.86

.88

.90

.92

.93

.95

.94

.92

.92

.92

.93

.95

.96

.96

.96

.96

.96

.96

.981.021.041.081.161.231.271.331.341.291.271.38

TOTRL-tlEV/FISSPU239 U235

239/235

.87

.90

.91

.92

.92

.93

.91

.90

.89

.89

.90

.92

.93

.93

.94

.94

.93

.93

.93

.95

.96

.981.021.031.031.01

.98

.82

.77

.83

00E+O100E+0200E+0200E+0200E+0200E+0300E+0360E+0300E+0300E+0400E+0400E+0400E+0464E+0400E+0300E+05Olx+os05E+0500E+0600E+0663E+0600E+0600E+0758E+0700E+0716E+0700E+0700E+0816E+0800E+09

/:2.

3.21E+O02. 60E+O02. 28E+O02. 08E+O01.95E+O01. 56E+O01. 27E+O01. 05E+O01.OIE+OO7.63E-016.27E-015.15E-014.38E-014.13E-013.97E-013.35E-012.91E-012.70E-012.45E-012.13E-012.00E-011.82E-011.46E-011.26E-01

3. 66E+O02. 85E+O02. 48E+O02. 27E+O02. 13E+O01.72E+O01. 44E+O01.21E+O01.18E+O08.99E-017.26E-015. BOE-014.8SE-014.56E-014.37E-013.70E-013.25E-013.03E-012.75E-012.37E-012.22E-011.99E-011.54E-011.34E-Ot1.24E-011.07E-019.92E-027.44E-025.83E-023.41E-02

.88 3.19E+O0

.91 2.78E+O0

.92 2.51E+O0

.92 2.33E+O0

.92 2.20E+O0

3.71E+O03. 16E+O02. 77E+O02. 54E+O02. 37E+O01.91E+O01. 62E+O01. 37E+O01. 33E+O09. 99E-018.13E-016. 79E-015.87E-01S. 56E-015. 35E-014. 49E-013.74E-013. 30E-O 12.74E-012. WE-O 11.73E-011.37E-018.1OE-O26. OOE-025.14E-024.1 OE-023.85E-023.46E-022.93E-021.77E-02

6.41E+O0 7.37E+O05.38E+O0 6.00E+OO4.7BE+O0 5.25E+O04.41E+O0 4.80E+O04.16E+O0 4.50E+O03.37E+O0 3.64E+O02.78E+O0 3.05E+O02.32E+O0 2.59E~O02.24E+O0 2.51E+O01.68E+O0 1.90E+O01.39E+O0 1.34E+CI01.16E+O0 1.26E+O0l.~E+OO 1.07E+O09.46E-01 1.OIE+OO9.1OE-O1 9.73E-017.66E-01 8.19E-016.51E-01 7.00E-015.8SE-01 6.33E-015.13E-01 5.50E-014.16E-01 4.37E-013.80E-01 3.95E-013.29E-01 3.36E-012.40E-01 2.35E-012.00E-01 1.94E-011.BIE-01 1.76E-011.49E-01 1.48E-011.35E-01 1.38E-019.1OE-O2 1.09E-016.74E-02 8.76E-024.29E-02 5.18E-02

3.4.

4:3.4.1.

::

::1.2.4.6.

;:2.4.

;:2.3.

.90 1.81E+O0

.88 1.52E+O0

.86 1.27E+O0

.86 1.23E+W

.85 9.17E-01

.86 7.5%-01

.89 6.44E-01

.90 5.61E-01

.91 5.32E-01

.91 5.13E-01

.91 4.31E-01

.90 3.!59E-01

.89 3.18E-01

.89 2.68E-01

.90 2.03E-01

.90 1.79E-01

.92 1.47E-01

.94 9.40E-02

.94 7.35E-02

.93 6.52E-02

.88 5.4SE-02

.84 5.14E-02

.62 4.46E-02

.52 3.73E-02

.54 2.44E-02

1.16E-019.48E-028.37E-024.65E-023.00E-021.84E-02

4.

::1.

TASLEb

FISS1ONPRODUCTBETADECAY POWER (liB)

ExDerlmental239

Pu Valuesand PPICIU-PUResults

TASLS 5

F2SSIONPRODUCTCAMA DECAY PC41ER(Hy)

Sxueriu.ental239FuVdw8 and FPIC/U-P”Res”ltz

235U239p”~a=t ~i,,iOn l%ermalFission

Z Difference Z DifferenceExperiment FPIC from FPIC from

(W) (u )w Experiment QWJ P.xperiment

Z35U

YheamalFiss;o”% Difference

239Fsst Finsion

% DifferenceEnpeki.ent FTIC from

(“w) QIWJ Experimentt

s!s!!4k@lY.Qt

ak!k@!YQPPIC fromQWJ Swerlment

2 46 286 243 -15.0 290 1.6 2 .466776

339 340 0.3232 238 2.6198 211 6.6172 179 4.1136 144 5.9

357 5.3246 6.067

76218 191 -12.4201 177 -11.9

219 0.4198 - 1.5 217 9.6

183 6.490i10144

179 160153 141127 119

-10.6- 7.0- 6.3

173146113

- 3.4- 4.6-11.0

90110 147 8.1

105 11.7

308 23.2263 24.0213 25.3161 25.8120 20.0

325 16.9277 21.0224 20.4168 25.4125 12.6

144 94 103 9.6

250 293 17.2212 253 19.3170 207 21.8128 158 23.4

3 54627597125

211L 220217 200188 176153 1.48131 127

- 8.7- 7.8- 6.4- 3.3- 3.1

- 5.8-10.7- 8.5- 8.9- 4.4

256229195158125

2682.40204164130

6.25.53.73.3

- 4.6

10.33.02.5

- 3.0- 5.1

3 34627597125

4 53617496124

100 118 18.0

278 308 10.8229 266 16.2186 217 16.7134 165 23.1111 123 10.8

243 229233 208199 182169 154137 131

4 53617496124

7

T6SLE 6

FISSIONPRODUCTTOTAL DEaY Pm (Ksti)TABLE 7

BETA DECAY POWER CONTRIBUTIONSFROM DOMINANT ISOTOPESIherimental

239Fu Values snd FPIC/U-FuResults

FPIC/U-Pu Instantaneous Burst Calculations*

235U239

h Fast Fission Them~l FissfonZ Difference Z Difference % Contribution

239PU 235UExperimentPPIC@F&& (u )w O.!Q

fromSmeriment

-6;9-4.7-2.8-3.4-1..40.4

4.55.67.08.96.1

FPICw

647665415356293218

564492408

fromExDerimemt

& Isotope ~ Thermal2 46 625 58367 450 42976 399 38890 351 339110 289 285144 221 222

3 54 49L 51362 429 45375 35.9 383

2s1 3061:; 231 24S

3.53.34.01.41.4-1.4

14.914.714.013.56.1

144140pr

‘*a)143~9Pr

Sr

14 1413 1312 219 8

~~

56 74

50

319245

SUM

144140pr

91~a) 1~2

14327

*9Pr 1 1Sr _9~

4 53 521 537 3.1 593 13.861 462 474 2.6 517 11.974 385 399 3.6 428 11.296 303 319 5.3 332 9.6124 248 234 2.4 255 2.8

100 25 28

where A and x are constants to be determined, t is

time after shutdown, and T is time of operation at

constant flux f. Ml times are given in daya. The

macroscopic fission cross section is given by the

usual notation, Nu. Each aet of beta, gamma, and

total decay power data waa fit and averagea were

taken. Then, in the limit as T + O, expressions

for the inatentaneous burst of fissions were de-

rived. In the process of comparing the experi-

mental decay powera with those calculated for the

experiment by uae of the analytical fits, inconsis-

tencies were discovered, especially for sample 4.

When these difficulties were brought to his atten-12

tion, Johnston revised his analytical fits so

that Eqa. 4 to 6 of Ref. 10 now read (H in watts)

51 78SUM

144140pr

91~a)143~9Pr

Sr

33 440 0

10 220 0

J 13—

48 79

175

ISUM

(a) This isotope waa added to the FPIClibrary.

TABLE 8

GAMMA DECAY POWER CONTRIBUTIONSFROM DOMINANT ISOTOPES

FPIC/U-Pu Instantaneous Burst Calculations

% Contribution239PU 235U

Fast Thermal‘w = 1.93 x 10-13 w f[~o”2’ - (t + T)-o”z’]

Qi!d50

100

175

Isotope

95~5Zr

lo3Nb106~

SUM

;;;:

Rh

SUM

95zr

95N7J103106~

SUM

(2)

HV = 1.57 x 10-13 Ncs f[t-o”53 - (t+ T)-o”531 18 191.5 1615 71 0— —

49 42

28 3237 4317 9~~

85 84

28 3250 5710 5~ &

94 94

(3)

H;= 1.62 X 10-13 No f[t-o”06 - (t+ T)-o”06],

(4)

where t and T are in days. For an instantaneous

burst, the derived equations now becoqe (cf. Table

3 of Ref. 10)

“fl+y= 6.48 X 10-19:1”2’ W/fias (5)

Hy = 9.63 x 10-19 t-1-53 Wlfiaa (6)

HB = 1.12 X 10-19 t–1.06

W/fisa . (7).

8

.

The revision of the composite fits as given above

stems from changes in the coefficients of the

individual fits for sample 4. As given on p. 31 of

Ref. 11, the equations for sample 4 should now read

(H in watts)

HB+y= 1.84 x 10-13 NCY f[t-o”z’ - (t + T)+”27]

(8)

Hy = 1.59 X 10-13

No f[t-0.54

- (t+ T)-0”54]

(9)

HB = 1.84 X 10’13 No f[t-0”05 - (t + T)-0.05

1.

(lo)

Additional comparisons have been made between

the FPIC/U-Pu calculations following an instantan-

eous burst of fissions and Johnston’s analytical

fits as given in Eqs. 5, 6, and 7. Both the 239Pu

fast fission and the235

U thermal fission libraries

were used for the FPIC/U-Pu calculations. Plots of

the three sets of calculations are shown in Figs.

1, 2, and 3 for beta, gamma, and total decay powers,239

respectively. The comparison for Pu fast fis–

sion shows a significant improvement over those

which were reported using the old analytical

fits.13 Whereas the maximum differences between

calculated and experimental decay powers were 6%

for total, 25% for gamma, and 20% for beta,13

With

the new fits the corresponding figurea are 7%, 21%,

and 14%. On the basis of the new comparisons, it

aPPears that the use Of the239

Pu fast fission,235

rather than U thermal fission yields, generally

improves the agreement of the summation calcula-

tions with Johnston’s analytical expression for

gamma and total decay power (Figs. 2 and 3). The

beta decay power, however, still shows best agree-

ment of Johnston’s analytical expression with the235

U thermal fission summation calculation (Fig. 1).

Before drawing conclusions as to the superiority of

either set of fission yields, however, it is well

to examine the errors inherent in using the ana-

lytical fita.‘he ‘its ‘0 ‘he data ‘Or HYadH&Y

for each individual sample are reported by Johnston

to agree with the data within the experimental11

errors. The resulting best fit for all samples

combined had an added uncertainty due to variations

among samples. In the case of the HB fits, the

constants for Eq. 1 differed very significantly

among samples, giving least confidence in the HB

analytical fits. The accuracy of the fits in repro-

ducing the experimental data from which they were

derived is discussed later. In any event, the gen-

eral agreement of the instantaneous burst summation

studies with the derived fits follows the same

pattern as the comparisons for the reproduction of

the experiment; i.e., the gamma and total decay

powers agree best between the experimental results239

and the Pu fast fission summation study, while

the beta decay power agrees best with235

U thermal

fission results. It might be well to point out now

that comparisons of measured239

Pu fast fission

decay powers with235

U thermal fission summation

studies may seem like what the late K. T. Spinney

c.illed an “inspired extrapolation of irrelevant

data.” However, since these irrelevant235U ther_

mal fission data are the choice of many fast reac-

tor shielders, and the experimental data for yields

from239

Pu fast fission are obviously still quite

sparse, the comparisons are not completely unjusti-

fied. As was mentioned previously, an additional

uncertainty arises from the different spectra of

the neutrons inducing fissions in the experiment

and calculations.

In connection with these comparisons, it is

interesting to examine the source of the difference

between the239

Pu fast fission and235

U thermal

fission summation calculations for beta and gamma

decay powers. By observing the percent contribu-

tion of the dominant isotopes contributing to the

respective beta and gamma decay powers in the two

cases, the effects of the different yields from239

Pu fast fission and235

U thermal fission can be

observed. Table 7 summarizes the contributions

from the five principal contributors to the beta

decay power after an instantaneous burst, and Table

8 does the same for the four principal gamma con-

tributors. The largest variations naturally occur

for mass chain yields near the top of the steep

slopes of the mass chain yield curve, where the

yields are most sensitive to slight lateral shifts89 9+ show this behavior.

in the curve. Sr and

COMPARISON OF ANALYTICAL FITS WfTH EXPERIMENTALDATA

Johnston’s data were further exsmined from the

point of view of the accuracy with which the ana-

lytical fits represent the experimental data. Thus,

9

lo-m~“””~

I o FPICOU-PU U-235 BETR

O FPIC/U-PU PU-239 BETR

● JOHNSTON PU-239 BETfl

,0-22

.

.

.

10 ‘1 I I 1 1 I I 1 I 1 i 1 1 I I I I.

10 zTIME RFTER BURST -- DRVS

Fig. 1. Fiesion product bata decay powers following an inotenteneoueburst of fieeione.

calculation were performedwith the analytical

fite given in Eqs. 2, 3, and 4 for an operating

history duplicatingthe experimentalone. The239

reeulting 1% fast fieeion decay powere and per-

cent deviation from the experimentalvaluee are

shown in Tables 9 through 11. In Table 11, the

total decay power wae computed both by the equation

for total decay power iteelf (HBW) and by aming

the equatione for H and H .By

One minor ●ource of error in duplicating the

operating history may be the following:

10

The reproductionof the reactor operating himtory

.

103

ueing the analytical fite wae performed for each

of the individual irradiation periods (6 periode

for eample 2 end 10 periods for eamplee 3 and 4)

ehown in Table 1 of Ref. 11, whereae the derivation

of the fite wae performed for the average flux over

each operating period (4 periode for eample 2 and

6 periode for ●amplen 3 and 4). In each caee where

.

a mean flux

irradiation

such period

wae ueed by Johnston for contiguous

periode, the flux during the penultimate

wae lower than during the laet one.

, ~-20

I “’’’’’” “’’’”

o FPIC4J-PU !,)-23S TOTRL

o FPICAJ-PU PU-239 TOTA

● JOHNSTON PU-239 TOT*

,0-22

It

1 t I 1 1 1 I I I 1 I L 1 I I 1aI

10 zTIME ~FTER BURST -- D#WS

Fig. 2. Fiamion product g-a decay pwera followiog am inmtentaueouaburst of fiesionn.

Since the laet irradiationhae the greater relative

importance, this would tend to increaee the calcu-

lated valuee of HB’ ‘y’ and ‘MY”

However, no euch

trend is visible in the data of Tables 9 to 11.

Johnston’s analytical fitting wae performed for

each individual eample separately, and then the

constanta for each sample were averaged (arithmeti-

cally) to get a single equation to represent the

data from all three samples. In order to isolate

this effect, each individual equation wae alao coded,

10 3

and the reeulte for H amd H are ehown in the lastBY

two columne of Tablee 9 and 10, respectively. The

agreement between experiment and the Individual

fite ie generallywithin the experimental errore

quoted by Johnston. The individual fits are, aa

would be expected, generally a better representa-

tion of the data than the composite fita. Although

not ehown in Table 11, values of H&Y

were calcu-

lated for each individual sample, and generally

agreed better with experiment then did the compos-

ite fit.

11

, ~-20.~”-~

o FPICAI-PU U-235 GW’lNfl

O FPICAJ-PU PU-239 GQMilfl

● JOHNSTON PU-239 GIW’lR

.

,0-22 I 1 1 I I 1 1 t I I t 1 1 I 1 I I I

10 ‘ 102 103

REFERENCES

TIME RFTER BURST -- OWS

Fig. 3. Fiaisionproduct total decay powers folloving an inetantaneouaburst of fimaions.

1.

2.

3.

S. K. Penny, D. K. Trubey, and J. Gurney, “l!ib-liography, Subject Index, end Author Index ofthe Literature Examined by the Radiation Shield-ing InformationCenter,” Oak Ridge NationalLaboratory Report, ORNL-RSIC-5(f@V.1) (1966),pp. 15-19.

J. F. Perkins and R. W. King, “Energy Releaeefrom the Decay of Fiseion Products,”&Sci. En~. ~, 726 (1958).

J. F. Perkins, “Decay of U-235 Fission Pro-ducts,” Redstone Arsenal Report RR-TR-63-11(1963).

4. K. O. Koebberling,W. E. Krull, and J. H. Wil-son, ‘%ockheed Fianion Product Inventory Code,”Lockheed-GeorgiaCompany Internal ReportER-6906 (1964).

5. L. Burrle, Jr., and I. G. Dillon, “Estimationof Fission Product Spectra in Discharged Fuelfrom Fast Reactors,” Argonne National Labora-tory Report ANL-5742 (1957).

6. L. E. Weaver, P. O. Strom, and P. A. Killeen,llE~tfmtedTotal chain and IndependentFiE#fouYields for Several Neutron-InducedFissionproceases,ltNaval Radiological Defense Labora-

tory Report NRDL-TR-633 (1963).

.

.

.

12

TASLS 9

FISSIONPROOUCTBETA DSCAY POWER FROfl239PuFAST FISSION—

Johnston’sAnalyticalFits ,md theEx~.?rLme”t.lD.IM

fromWhich They Were Derived

TABLE 11

FxssxoNpRoDUcTToT.fLD~y POWER FROM 239pu FAsT FIssIoN

J.ohmsto”*sAnalyticalFits and the S%perim.entalDatafrOmmich They Were Derived,Usinp,the C.mrpniteFit

for SIB* a“d the Sum of the CompositeFitsfor SIBand %ComPositeFit(a)

% Difference(b)IndividualFit(c)

% DifferenceFit from

.

.

t Experiment Fit fromX!PI!?.MYQ (“w) QIUJ Experiment

2 46 286 278 -2.867 218 215 -1.476 201 197 -2.090 179 174 -2.8110 153 149 -2.6144 127 120 -5.5

3 54 241 248 2.962 217 224 3.275 18S 195 3.797 153 160 .4.6125 131 131 0.0

.4 53 243 255 .4.961 233 231 -0.874 199 201 1.096 169 165 -2.4124 137 135 -1.4

(a)MS+Y

% Difference(b)

E +ff

% Difference

Fit from

M F.xuertment

282220202179

-1.40.90.s0.0

t&ekkL?Yd

Experiment(u )w

Fit

MQ

5S6426381326270207

514453379297231

528

from

Experiment ~ Emeriment

5S6 -6.242.4 -5.8379 -5.0325 -7.4270 -6.6208 -5.9

514 4.7452 5..3378 5.6296 5.3232 0.4

528 1.3

154125

239

0.6-1.6

-0.8-0.9-1.1-1.3-6.1

4.1-1.70.0-3.0-1.4

2 46

67

76

90110M4 .

625450399351289221

491429358281231

521

-6.2-5.3-4.5-7.1-6.6-6.3

4.75.65.95.70.0

1.3

215186151123 3 5.4

62253229199

7597

164135

125

4 5361 462 466 0.9 465 0.674 385 390 1.3 389 1.0

(a)

(b)

(c)

See Eq. 4. 96 303 306 1.0 305 0.712.4 248 239 -3.6 239 -3.6

John. &(lo) quotes a 95% confidencelfmit of ~7% for valuemofifsderivedfrom the analyticalfit. It does not, however,includethe error incurredin fittingthe data; i.e., the errorreflectedhere.

See equationson p. 31 of Ref. 11, for samplea2 and 3. (a) See Eq. 2.

(b) J.ahnston(lO)mmtes a 95% conflde”celimitof +6% for values of

%ti derivedfrom the analyticalfit. It does-not,however,includethe error incurredin fittingthe data; i.e., theerrorreflectedhere.

TABLE 10

FISSIONPRODUCT_ DECAY PCUERFROM 239PuFAST F2SSION

JohnmtOn’mAmalvticalFits and the ExDerlmentalOatafromWhich They Were Oerived 9.

10.

K. Shure and D. J. Dudziak, “Calculating EnergyReleased by Fission Products,” Trans. Am. Nucl.

a~, (1) 30 (1961).Compc..iteF,,(a)

% Difference(b)IndividualFit(c)

% Differencet Bxperfment Fit from

Samule (days) (“w) ~ ExuericxmtK. Johnston, “A Calorimetric Determination ofFission Product Heating in Fast Reactor Plu-

Fit

Il!!Q

34023120216813599

249213ii’z12794

2702311s6138102

from

Experiment

0.3-0.42.0-2.3-0.75.3

tonium Fuel,” ~ucl.-Energy, Parta A/Bti~,527 (1965).

2 46 339 308 - 9.167 232 20s -10.376 198 182 - 8.190 172 151 -12.2110 136 121 -11.0144 94 88 -6.4

3 54 25o 266 6.462 212 228 7.575 170 1s3 7.697 128 136 6.2125 100 101. 1.0

4 53 278 273 -1.861 229 234 2.274 186 189 1.696 134 140 4.5124 111 104 -6.3

11. K. Johnston and D. G. Vallis, “Fission ProductHeating in Fast Reactor Plutonium Fuel,” UKAtomic Weapons Research Establishment ReportAWRE-O-68/64 (1964).

-0.40.51.2-0.8-6.o

-2.90.90.03.0-8.1

12.

13.

K. Johnston, AWRE, private communication (1968).

M. E. Battat, Donald J. Dudziak, and H. R. Hicks,“Fission Product Decay from Fast Fission of239PU,!! Trans. ~. Nuc1. SOC. 10 (2), 524 (1967).—

(a) See Eq. 3.

(b) Job”.t.an(’o)quotesa 95% confidencelimitof tlO% for valuesofHy derivedfrom the analyticalfit. It deem not, however,includethe error incurredin fittingthe.data; i.e., the error reflectedhere.

(c) See equationaon p. 31 of Ref. 11, for a.amplea2 and 3.

C. A. Anderson, Jr., “Fission Product Yieldsfrom Fast (=1 MeV) Neutron Fission of Pu-239,”Los Alamos Scientific Laboratory Report LA-3383(1965) .

7.

8. K. Wolfsberg, “A Method for Estimating Frac-tional Yields from Low- and Medium-EnergyNeutron Induced Fission,” Los Alamos ScientificLaboratory Report LA-3169 (1964).

13

RPPENOIX R

THE CHQNGES MRDE IN THE U-235 THERM9L FISSION DRTFI OF THE LOCKHEEOFISSION PRODUCT INVENTORV CODE (FPIC> QRE LISTED BELOW. THESECH9NGES WERE INCORPORATED IN THE FPIC/U-PU CODE, THE INPUT DFITR FORWHICH FIRE GIVEN IN IIPPENDIX B.

1. RDDITION OF COMPLETE NUCLIDE DRTR FOR V-91. THIS WRS OMITTEDIN THE ORIGINFIL COMPILATION. FOR DRTIl USED> SEE ENTRV FORTHIS NUCLIDE IN FIPPENDIX B.

2. TE- 133R CHRNGE CUMULFITIUE VIELD - V(2> - FROM 5.4 TO 1.72PERCENT.

3. PD-110 CHFINGENUCLIOE IDENTIFICATION FROM PD-11O TO PD-112.4. CHRNGES IN OECWf CONSTFINTS. DECBY CONSTFINTS USED WERE OBTRINED

FROM JULV 1965 (EIGHTH EDITION> CHRRT OF THE NUCLIDES BYDWID T. GOLDMQN.

-NUCLIDE- -ITEM CHFINGED-

1-137 LFIMBDQ-2XE-137 LRMBDR-1

BR-89 LmlBDR-2

RB-91 Lf4MBDR-2SR-91 LFWIBDR-1

TC- 102M LRMBDR-1TC- 102 LIVIBDfl-1

RU-107 LFIMBD9-2RH-107 LFWlBD9-1

CD-1 18 LIX’IBD9-2IN-1 18 L9MBDQ-1

TE- 125M LRNBD9-1TE- 125M LmlBoFJ-2

TE- 127R LFNIBDFP2

BI+137M LfNIBDQ-1

CS- 142 LlwlBD9-2BR-142 LFWIBDI+l

-OLD URLUE-

2.89E-032.89E-03

1.50E-01

8.25E-048.25E-04

1.00E-031.00E-03

2.28E-032.88E-03

2.78E-042.78E-04

1.38E-071.1OE-O8

2.04E-05

7.39E-10

1.16E-021.16E-02

-NEW VFILUE-

2.89 E-022.89 E-02

1.54 E-01

9.G25E-039.625E-03

1.06 E-031.06 E-03

2.75 E-032.75 E-03

2.31 E-042.31 E-04

8.14 E-091.38 E-07

2.07 E-05

7.32 E-10

3.01 E-013.01 E-01

.

14

FIPPENDIX B

FOR REFERENCE PURPoSES, R LISTING OF THE NUCLIDE DECFIV D9TFI FOR U-235THERM9L 9ND PU-239 FQST FISSION tlRE SHOWN IN THIS 9PPENDIX. THESE Df2TFIRRE THE INPUT DRTR USED IN THE FPICA1-PU CODE. FOR EIICH NUCLIDE, FIUELINES OF DI?TR RRE SHOWN. DEFINITIONS OF THE SVMBOLS USED FIRE -

LINE 1

LINE 2

LINE 3

NUCLIDE =LFNIBDFI1 =LFIMBDR2 =V235THC1> =

V235THC2) =ECBETFI> =ECGFMW> =

V239F9C1) =

V239FFIC2) =

NFUIE OF NUCLIDEDECFIV CONSTFINT Cl/SEC> OF PFIRENTDECRV CONSTFINT Cl/SEC) OF NUCLIDEINDEPENDENT %’IELD (PERCENT> OF NUCLIDE, U-235THERMFIL FISSIONTOTRL VIELD (PERCENT> OF NUCLIDES U-235 THERM9LRUERRGE BETR ENERGV, MEU/DECIWFIUERFIGEGRMMFIENERGV, MEU/DECFIV

INDEPENDENT VIELD (PERCENT> OF NUCLIDE, PU-239FFIST FISSIONTOTFIL VIELD CPERCENT> OF NUCLIDE, PU-239 Ff3ST

GFNIMRENERGV CMEU/DECllV) FOR ENERGV GROUP EGCI)EGC1> 0.1 TO 0.4 MEUEGC2> 0.4 TO 0.9 MEUEGC3> 0.9 TO 1.35 MEUEGC4> 1.35 TO 1.8 MEUEGC5> 1.8 TO 2.2 MEUEGC6> 2.2 TO 2.6 MEUEGC7> GREFITER TH9N 2.6 MEU

LINES 4 FIND 5THE DOSE CONVERSION FFICTORS CREM/CURIE> FOR THE BOD%’ORGFINSLISTED RRE GIUEN. THESE DRTB REPRESENT CONVERSION FQCTORSFOR F!CCUMULFITEDDOSE FOR 70 VEflRS EXPOSURE FIND QCCOUNT FORTHE FRFICTION OF INHFILED NUCLIDE QCTIUITV THQT IS DEPOSITEDIN E9CH BODV ORGRN. EXCEPT FOR V-91, THE FIGURES 12REREPRODUCED FROM THE LOCKHEED-GEORGIR REPORT ER-6906. CREF 4)

-NUCLIDE -LRmml -LaNBm2 -V235THC1>-V235THC2>ECBETI?) -ECmr’t’ln)-V239F9CI>-V239FQC 2)

-EGc 1> -E~C2) -EGC3> -EGC4) -EGcs> -EGCG>-BONE -G. I.

-EG(7>-KIDNEV -LIWR -LUNG -MUSCLE

-PRNCREf4S -PROSTRTE -SPLEEN -TESTIS -THVROID -iMLEB~

GE77M 1.000EOO 1.280E-020. yxlE~2 7.71(E-01 1.--010.

1.95DE-01 o. 0. 0. 0. 0. 0.0. 0. 0. 0. 0. 0.

0. 0. 0. 0. 0.:;7 1.2BOE-02 1.71OE-OS 2.1ODE-O3 301~-03 6.37~-01 1.126E DO

2.000E-03 6.GOOE-033.030E-01 4.31OE-O1 1.660E-D1 1.DBOE-01 9.m-02 2.400E-02 O.0. ~.87SE 03 &521E 03 &975E 01 ~.520E03 0.

t$ie l:OmE w 9:170E-050. 2:OODE-02 i:Y&+Y o.

0.9.e20E-03 poE-02

o.&432E 02 j:464E 01 &D5E 00 &6B6E 02 ~:

o.0.

&;71a 1.2BGE+2 4:970E-06 ~:400E-03 $200E$2 ;:%-% 2.300E-02

1.600E-02 7.DOOE-03 o.3.679E 03 ;.= 02 &64E 02 ;:474E 03 !:

o.0.

0.&7B 1.71W-OS 4:97m-06 o: 3:1OOE-O3 ;:%-% 2.30DE-02

o. :: 000E-031.600E-02 7.ODGE-03 O.

3.67% 03 ;:209E 02 &64E 02 ~.474E 03 &o.

0.0. 0. . . 1.105EO2

15

-NUCLIDE -w=TKl EV2nw2)-ECBETR> -ECGRtlMR>-V239F3?C 1>-$’239FRC2)-EGC4> -EMS) -EQC6) -EGC7)-LIUER -LUNO -IIUSCLE-TESTIS -THVROID -WHOLEBOOV

-EGC1>-BONE-P9NCREfK

QS78

-EGC2)-(3.1.-PROSTIJTE

9.1 70E-OS

-EQC3>-KI~V-SPLEEN

1. 270E-04.

.

0. 2.moE-02 1.449E 00 8.830E-013.81m-04 3.~-026.1~-02 7.~-02 2.200E-02 3.500E-023.099E 01 :.053E 02 0.0. . 2.535E 010. 5.=-02 8.990E-01 O.3.6BW-03 7.~-02o.1.77GE 00 ;:536E 01 %

o.

0. . 1.41SE m

1. 600E-02o.0.

40290E-011.164E 030.1.000E 00

2. 470E-011.181E 020.1. 2BOE-03lw79

o.k 6.SS2E 010.

s&9rl 1.280E-03

9.600E-02 O.1.789E 00

& o.

0.G.790E 000.2.960E-03 5.600E-02 O. 9. 600E-02

3.2GOE-04 ;.000E-020.1.249E-01 ~:238E 00 ~:

o.

0. . 1.031E-01

0.5.900E-01o.2.030E-04SE81M I.000E 00

1.030E-01 O.0. 2.763E 010. 0.

0.9.IOOE 001.137E 00

--- - .0. 0.

9E 00ii937E 00 ;i920E 01 0.0. . 1.S8

SE81 1.160E-03 6.41OE-O4 1.320E-015. 390E-03o.1.280E 010.0.5.97=-02o.0.0.

1.400E-011.780E-010.S.32BE01 ::0. 4.431E 00

5.220E-01 1.SooE-ol

o.1.SOOE-01o.0.

SE83tl

o.7.728E 01 &274E 010. 1.237E 011.000E OO1O.OOOE-O3 2.m-ol

2.020E-011.O1OE-O1o.0.

1.379E W 2. 020E-O 1

0.9. 000E-03o.

2;3

1.600E-02 ~.600E-02o. .0.1.000E 00 t620E-04

o.0.0.5. 7GOE-01o.

5.970E-02o.2.06SE 010.

2.200E-011● 720E-013.120E-01:.592E 01

9:2mE-ol4.790E-01Q.

1.421E 00

0.3.200E-02o.0.

1.830E-01 1.31N-011.245E 02 ;.33~ ~~o.1.000E 00 3:8SOE-03

o.::0. ::1.000E 00 1.7BOE-02

o. 0.0.

0.0. 0.0. 0.

s&7 1.000E 00 4.330E-02

7.630E-01o.7.154E m2.400E-01SE84 3.000E-01

o.

0.2. 770E-01

&o.0.4.130E-01o.0.0.

3.000E-01o.

!&s

o.

::1.610E-01

o.0.1.1OOE 005. 220E-olo.0.0.

0.

0.0.0.0.l.lowmo.

2.=-01o.

;: o.. 0.

2.000E 002.640E-01

o.

0.0.

&o. 0.0. 0.0. 0.

1O.OOOE-O3 8.370E-OS

o.0.0.3. 360E-01

o.0.2.890E 01

BR83Q 0:6. 230E-03o.

k

2: 900E-011.8eoE-olo.3.278E 020.

4.000E-03

o.0. 0.0. 4.738E 02 &o. 0. 0.

BR83B 4.620E-04 8.370E-OS o.0.0.0.0.

2. 200E-011.920E-01

3.360E-01 4.000E-03

o.0.0.0.

0.4.738E 02 &o. 0.

0.0.2.890E 01

0.3.278E 020.

BR84M 1.OWE 00

8.670E-01o.0.3. 8SOE-03

1. 920E-03

3.630E-01

o.2.000E-023.190E-01o.0.0.:. px~:

o:0.20OmE-ol1.620E-010.0.0.

1. 900E-022.1OOE-O27.41OE-OIo.0.9.2mE-ol4.990E-014. 120E-013.83BE 020.l.lmEoo;. 840E-01

1:836E 010.

7.1OOE-O1

1.660E-01o.0.1.226E m

3.276E 00

7.S80E-016.200E-02o.0.

0.0.

BR84 3.61OE-O4 1.821E 00

4.21OE-O13. SOOE-02o.

I&

4. 82W-01~.544E 02

1: 780E-02

2. 020E-ol 9. 200E-02o.3.420E 011.037E m

0.0.3. 8SOE-03 o.

0.&o.

0.2.646E 01 ~:o. 0.

0.0.1.63SE m

16

-MJCLIOE -V23STHC1)-V23SM2>ECBETQ) -EC~>-VZWM 1)-V239FQC2)-EOC4) -EQcs) -EQCG> -EQ<7>-LIUER -LLM -~-TESTIS -THYROID -WIOLE~

-EQC1>

-PRfw?ms

BR87

-EGC2>-G. I.-PROSTRTE

4. 330E-02

-EGC3>-KIONEV-SPLEEN1. 260E-02

#

.

0. 2.4WE m 1.873E m 3.7%OE 006.91 OE-O1 ~. SSOE-01o.0.

0. 3.7%OE 000:

0.0.

0. 0.&o.

BR88

&o.1.000E 00

0.0.0.4. 330E-02 o. 2.61OE W 3:400E-01 O.

7.4SOE-01 :.490E-01

&o.

0:0.

0.0.

0. 0.0. 2.seoE m o. 0.5.41 OE-O1 5.67W-01

&0.

::0.

o*0.

0. 0.

0.0.

B&9

o.

::1. WOE 00

0.

::1.540E-01

o.0.

K&1

o.0.0.0. 37E-05

o*0.0.1.O1OE-O4 o. 5. lmE-ol o. 4. 1OOE-O2

1.230E-OS ;.WOE-01

::. 0. 0.

0.0.

& o.0. 1.300E 00 2.830E-01 1. 780E-012. e90E-03 & 870E-01o.0. 5:411E 02 ~:

00

0. 0. .

::0.

KRWUI

o.0.0.3. 8SOE-03

o.

R4. 3eoE-os

1. 7BOE-01o.0.

KR85

o.7.825E 02 ~:o.

2: 070E-094. 300E-05 o. 2.930E-01 2.21 OE-O1 4.000E-032. B90E-03 & !$77E-01

:: 2:454E OS ;:o.

0. 0.

4. 000E-03o.0.

0.G.335E 030.

0.

&KR87 1. 260E-02 1. 4%OE-04 o.

1.91 OE-O1G.200E-02o.

&E-olS.430E-012.090E-010.0.2.O1OE 001.03m+oo1.IOSEOOo.0.

2:490E 001.145E+O0o.B.388E 02

:: ~gl

s. S30E-ol1,343E 030.4.59m 001● 59eE+ooo.3.336E 010.

i:335E m 1.091E 00

0.0.0.

K&3

4.G20E-011.212E 030.4. 330E-02

::0.6. %WE-OS

4. 600E-02o.0.3.61OE-O3

!5.670E-01o.0.3.730E-01 1.e97E 00

0.9. 300E-02

i

1.e7w-ol1.123E 030.1.S40E-01

e. 09aE-olo.0.1.3%9E mKRB9 2.33(IE 00

1.225E 000.0.0.

KR90

o.4.818E 010.

0.0.0.

0.0.0.

4.330E-01 2. 100E-02

930E-02

31OE-O1

0.1.21eE+m0.0.0.0.9. 990E-01o.0.0.0.5.330E-01o.

!:

ioomm1. 463E+Wo.0.0.3.4SOE 001.071E+O0o.0.0.

m o.

0.0.0.

K%

o.0.00

0.0.0.6.

0.0.0.

1,00CE00 1.200E m o.0.0.

0.0.

KR92

::0.1.000E 00

0.

R2.

0.0.0.0.1.670E m

S.460E-010.0.0.

0.

0.0.

::KR93

0.0.0.

o.

!:1.000E 00 3*460E-01 o. 4.WOE-01 0: 0.

1.830E-01 ;.%40E-01o. 0.0.

0.0. 0.

0.0:

0.

0. 0. 0.0.

0. 0.6.88=-05 6.420E-04 6.000E-02 3:57(IE 00 i:984E 00 7.4BOE-01

3.790E-02 1.430E+O01.560E-01 O.3.93GE 02 0.

2.300E-02 5.030E-01 o. 6.600E-024.S94E 01 ~.72SE 02 $.~SS ~~

o. 4.oeeE 01 0.3.G1OE-O3 7.700E-04 2.000E-01 4:790E 00 5:9f30E-01 2.394E 00

1.990E-01 1.797E+O09.%OOE-02 1.444E m 6.1OOE-O2 3.060E-01 3.340E-01 1.51OE-O14.4e2E 02 0. 4.3%3E 01 ~.100E 02 2.90%E 010. 3.731E 01 0. . 2.770E 01

0.0.0.

RB%9

o.0.0.

17

-NUCLIDE -LRPBDR1 -L-2 -V235THC 1>-V235THC2)-EC8ETFI) -E(~RJ-V239FRC 1)-V239FRC2)

-EGC1> -EGC2) -EGC3) -EGC4) -ED(5) -EGC6) -EGC7>-80NE -G. I. -K IDNEV -LIUER -LUNG -IIUSCLE-PRNCRERS -PROSTI?TE-SPLEEN -TESTIS -THVROID -WHOLE80DV

RB90 2.1OOE-O2 4.280E-03 7.7WE-01 5.770E 00 7.500E-01 4.944E 00

0.6.270E-01 2.090E+O0

8.400E-02 1.300E-01 1.900E-01 1.S1OE-O1 1.500E-01 4.21OE 000. 6.263E 01 0.

0.7.954E 00 ;.332E 01 4.067E m

7.224E 00 0.R&91

3.877E m6.930E-02 9.62SE-03 1.980E 00 5:430E 00 1.270E 00 3.000E 00

0. 0.1.346E+O0 &417E+O0

1.518E 02 &o.

0. 1.926E 01 &049E 02 %838E m3.000E m

o. 1.747E 01 0.R&2

9.360E DO2.31OE-O1 8.660E-03 3.43W m 5:300E 00 3.435E 00 0.

0. 0.1.896E+W ~.440E+O0

o. 0. 0. 0.0. 0. 0. 0. 0: 0.

0.R;43 3.460E-01 ;:240E-01 &620E 00 hOE 00 !:670E m O.

0. 0. 0.~.770E+oo &.954E+m

o. 0.0. 0. 0. 0: 0: 0.0. 0. 0. 0. 0. 0.

SR89 7.700E-04 1.600E-07 O. 4.790E 00 5.550E-01 O.

0.3.26=-03 &.800E+O0

2.996E OS $405E 04 &o. 0.0.

0. 0.I:777E 05 &

o. o*SR90

1.222E 044:280E-03 7.84OE-10 0. 5.770E 00 1.730E-01 O.

0.3.O1OE-O2 $120E+O0

1.388E 07 $479E 03 i:0.

2:164E OS &o.

0.0. 0. 0. 0. 4.780E 05

SR91 9:625E-03 1.980E-05 3.800E-01 5.81OE 00 6.240E-01 6.960E-01

o.1.81OE-O1 2.598E+O0

2.620E-01 2.800E-02 ~.080E-01 9.800E-02 0. 0.2.624E 03 ;.715E 03 0. 3.968E 03 0.0. 0. 0: 0.

SR921.892E 02

8:660E-03 7.400E-05 O. 5.300E 00 2.130E-01 1.274E 00

1.400E-02 2.800E-02 O.G.870E-01 3.127E+O01.232E 00 0. 0.

5.11OE 02 ~.597E 03 0. 0.0. 0.

1.183E03 %o. 0. 5.270E 01

SR93 1:240E-01 1.41OE-O3 O. 6.1OOE 00 1.269EO0 1.093E 00

0.1.087E+O0 3.641E+O0

4.000E-01 4.360E-01 &70E-01 O.7.584E 01 &

o.8.848E 01 ;.102E 02 0.

. 0. 0: 0. 3.612E 00S%4 2.390E-01 8.880E-03 2.30DE 00 5.200E 00 1.065E 00 9.300E-01

3.000E-02 O.2.746E+O0 ~.884E+O0

9.000E-01 O. 0.1.500E 04 ;.859E 01 0. 0. 1:286E 01 &

. 0. 0. 0.$&o

6.120E-017.84OE-10 3.~-06 O. S.770E 00 9.230E-01 O.

1.080s-04 :.120E+O0o.1.565E 04 ~:565E 04 $

0. 0. 0.0. 1:967E 04 0.0. 0. S.985E 02

V%M 1:980E-05 2:31OE-O4 O. 3.4- 00 0.9.980E-04 ;.559E+O0

5.420E-01

o. 5.420E-01 O. 0. 0.4.005E 00 &543E 02 0. 0. 1:067E 02 &

o. 0. 3.17s m&91*s SEE”FINRL EN% IN THIS TR8LL9TIONV92 7.400E-05 5.350E-05 7.30W-01 6.030E 00 1.431E 00 3.400E-01

2.2SOE-02 3.150E+m2.400E-02 2.4DOE-02 1.470E-01 ;.300E-02 6.900E-02 4.300E-02 0.1.181E 01 $706E 02 ~.o.

3.253E02 O.0: 0.

V939.705E m

1:41OE-O3 1:920E-05 O. 6.lWE 00 1.170E m 1.030E-011.570E-01 30799E+O0

1.900E-02 5.000E-03 2.600E-02 ~.100E-02 4.1OOE-O21O.OOOE-O4 0.3.691E 03 &947E 03 0. . &21SE 03 0.0.

V941.857E 02

8:880E-03 &080E-04 hOOE-01 5:400E 00 2.233E m 1.160E 007.WOE-01 4.584E+O0

o. 4.S80E-01 ;.020E-01 O.1.941E 02 $685E 02 :. 3.243E 02 %

o.

0. . . 0: 0. 9.652E 00

.

.

18

-NUCLIDE -L~l -L-2 -W~~l)-V2~TK2>-EC=TR) -E(WUINR)-V239FRC1 )-V239FRC2)

-EQC1) -EQC2) -EGC3> -EGC4) -EGcs) -EGC6) -EGC7)-BONE -G. I. -KIONEV -LIUER -LUtUJ -tUJSCLE-PRNCRERS -PROSTI?TE -SPLEEN -TESTIS -THVROIO -WEBW’f

V95 1. 730E-02 1. 100E-03 1.000Em1.912E+O0

6.= 005. 176E+O0o.9.7B4E 010.

6. 160E-01 9. 000E-01

o.0.7.706E 010.

0.1.430E 020.1.IOE-03

0.0.2.932E 001.180E-01

90WOE-01 :.0.0. 0:

7.310E-01

o.

ZR95 1.230E-07 0.1.230E-01o.1.272E 040.

6.2U)E 00S. 299E+O0o.2.061E 050.5.900E 005.136E+O0

7.31OE-OI1.473E 040.I.000E 00

0.3.es9E 041.15BE 04

0.0.8.200E 037.050E-01

o.0.1.41OE 02

0.2.861E 040.

ZR97 1.450E-01

o.

1.130E-05 1.600E 001. 444E+O07. 1OW-O23.960E 020.

0.1.704E 030.

NB95M

2.350E-01o.

Nh

1.200E-026.485E 030.1.230E-07

o.0.0.1. 230E-07

6.200E-021.278E 033.833E 022.140E-06

o.4.715E 030.1.200E-011.058E-01o.

2.350E-01

o.

0.

0.

0.3.030E-04o.0.0.

0.0.0.2. 290E-07

o.0.

0.0.

0.3. 030E-04

7.620E-01 O.2.863E 03 ~.;;~ ~; ;:534E 020.

1:160E-02 “

G.20W 005. 299E+O0o.4.S19E 030.S.wx 004. 3ooE+mo.0.

4. 600E-02 7.620E-01

o.0.8.63SE 01

N&7M

o.0.1.382E 020.1.130E-05

7.500E-01

o.0. moE+oo

;:o.1.900E-016. =-02o.3.539E 010.

7.!SOOE-01

o.0.0.

N%7

o.0.0.1, S60E-04

o.0.0.

0.0. 0.i:130E-05 6.090E m

5. 200E+O04.650E-01 6.690E-01

o.&350E 01

NA8

6.590E-015.563E 020.

0.0.1.147E 011.086E m

o.3.8SOE 020.6. 400E-025. 497E+O09. ooaE-02o.0.6.060E 005. 765E+O0o.0.0.

1.00= 00 2.260E-04

6.170E-01o.0.4.820E-03

0.0.0.3.850E-03

o.3.43w-ol1.61OE-O1o.0.

2.260E 00

0.!:o.

1.392E 000.0.2.1OOE-O2

o.0.0.1.360E mNB99 3.600E-01

o.

0.1.173E+O0000.0.

3.600E-01o.0.

0.0.0.l.omE m103OOE 000.0.4. B20E-03

9. 600E-029.038E 030.

0.0.0.1.451E 00NB100

3.890E-01o.

H:;9

o. 6.300E 002.S55E+O0 ~.;;~~o.0. 0;0.

3.51OE 00

1.007E 000.0.0.2.890E-06

4.11OE-O1o.0.4.040E-01

o.6.060E 005. 800E+Wo.~.S28E 01

0.3.520E-02o.3.246E 030.

1.190E-01

o.2.000E-028.200E 000.

0.1.S84E 040.7.700E-04

o.0.5.918E 024.200E-01

u.MO1O1 1.160E-02

5.S40E-011.373E 020.1.000E 00

0. 5:OOOE 006.830E-01 5.989E+O02.890E-01 2.670E-012.216E 01 ~.S28E 010. .

1.677E 00

0.1.51OE-O1o.

m;io2

4.160E-011.848E 020.1.060E-03

o.0.7.351E 004.360E-01 o.

0.

0.1.572E+O0

4.1OOE 00S.936E+O0o.;.350E 01

.

0.0.

rn;i os

o.0.1.820E ~

o.3.402E 01 ;:796E 01 ~:47SE 000. . –*l.oow 00 S.780E-03 o. 9.000E-01

o. :“%&;; :“70=+001.911E 02@Ol ~~636EOlo.3.21 OE-O5 O.

3. 83DE-05o.5. 2BOE-01o.

1.740E 00 1.500E 00

0.0.0.0.

::546E 010.2. 89m-06

o.0.5.122E W

TC99M 5.270E 005. 044E+mo.1.70BE 020.

0. 1.420E-01

o.1. 420E-013. 200E-02o.

0.2.470E 020.

0.1.441E 010.

0.0.8.155E m

19

-NUCLIDE -LFlllBDIll -IAmm2 -V235THCl >-V235THC2>-E(mTf)> -E(GIIflMR>

-V2391VK 1>-V239FRC2>-EGC 1> -EGC 2> -EGC3> -EGC4) -EGC5> -EGCG>-BONE

-EGC7)-G. I. -KICNW -LIUER -LUNG -flECLE

-PRNCRERS -PROSTRTE -SPLEEN -TEST IS -THVROID --EBOO’T’TC101 7.700E-04 8.2SOE-04 O. 5.OWE 00 4.790E-01 3.150E-01

2.760E-01 3.900E-02 O.1.lsuE-02 G.000E+OO

1.570E-01 ;.253E 01 ;.204E 01 &60E41 $712E 01 &o.

0. . . . . 3.370E m .TC102M 1O.6OOE-O4

o. 0.0. 0.

T:i 02 %600E-04

o. 0.0. 0.

0.T; i 03 1.000E 00

& ::0. 0.

TC104 4.620E-03

2.230E-01 ;.790E-01o.0. 0:

TC105 5.780E-03

4.2SOE-01 ;.250E-01o.

0:T:i 07 I.000E 00

0. 0.0. 0.

0.Rtl 03 9. 620E-03

2.000E-03 4.870E-018.162E 02 ;.900E 030.

RU10!5 1:160E-03

4.400E-02 5.700E-016.203E 01 ;.042E 030. .

1, 390E-01 o.3.21OE-O20.

&o.3.21OE-O2o.0.0.

2.OSOE 003. oou+m2.200E 000.0.2.OSOE 0030000E+OOo.0.o*3.000E m5.848E+O0o.0.0.1.800E 005.58GE+O0o.0.0.9.000E-O!5.230E+O0o.0.0.1.900E-013.142E+O0o.0.

7. 930E-01 2.200E 00

0.0.0.0.2.!570E-03

o.0.0.1.788E m o.

0.0.0.0.9.G20E-03

0.0.0.1.025E m

o.0.0.9.780E-01

0.

0.

0.2.550E-01o.0.0.

&o.

9.020E-01

o.

G.420E-04 o.7.280E-01

o.0.0.1.160E-03

o.0.0.6.S60E-01

o.0.0.

1.700E 00

0.

0.1.S23E+O08.SOOE-01o.0.

0.0.0.2.000E m

o.0.0.1.160E-02 o.

0.

0.2.202E+O0o.

&

o.0.

0.0.

0.2.CCWE-07 o. hoE 00

t.9SOE-03 ~.8SOE+mo.0. 1:034E 050. 0.

h30E-024.890E-01

o.0.1.078E 040.4.370E-OS

o.0.6.612E 02

6.SOOE-01

o*

o.7. 020E-02

3.4WE-02 2.000E-032.S06E 03 0.0. 0.

9.000E-015. 300E+O0o.1.412E 030.

4.160E-01

o.0.4.339E 01

RU106 1.000E 00 2.180E-08 00 3.8OOE-O11O.OOOE-O32.420E-01 ~:698E+00o.0. 9.179E 03 &o. 0. 2.294E 01

0.

0.0.1.377E 02

R&07

o.3.043E 02 ~:434E 020.1.160S-02 2:7SOE-03 1.380E-01

o.

0. 1.900E-01 1.671Em5.46u-ol ::688E+Wo.0. 2.736E 01 %

o. 8.639E-01& 3.moE m o.5.070E-07 ;.850E+O0o. 0.4.760E-01 ;:188E 01 0.0. . 4.935s-010. 1.--01 0.1.21UE-04 &060E+O0o.0. 0: !:o. 0. 0.

2.900E-02 6.800E-02 4.1~-022.417E 00 $969E 01 ;.OSIE 010. . .

RH103M 2.000E-07 2.030E-04 4.000E-02

o.

RH105M 4.370E-05 2.31OE-O2 1.290E-01

o.1.290E-01o.0.

0. 0.0. 0.0.4.370E-05 ::3SOE-06RH105 0. 9.moE-ol 1.680E-01

1.21=-04 ~.30CE+O0o.1.589E 02 j625E 03 &o. 9.646E 010. 3:800E-01 1.411E m2.11OE-O3 4.700E+O05.000E-03 $OOOE-031~.OOOE-04o.0. 0: 0:

3.200E-02

o.

.

3. 200E-021.607E 020.

RH106

0.2.860E 03 ?:371E 030. 4.491E 02

2.21OE-O1

4. 000E-03

2.180E-08 2.31OE-O2

1.81OE-O1 ~.700E-02

& o:

0.0.0.

20

-FUJCLIDE -LfW’Wlfll -L-2 -V23STHC1)-V23STHC2)-ECWTR) -ECcwlm)-V239fRC 1~V239FQC2)

-EGC1> -EGC2> -EGC3) -EOC4) -EMS) -EOCG) -EQC7)

-BONE -G.1. -KIBiEV -LIUER -LUNG ~-PRNCRERS -PROSTRTE -SPLEEN -TESTIS -THvRmo -wuE8wv

RH107 2. 7SOE-03 5. 2SDE-04 o.1. 180E-02o.5.e24E 000.

1.900E-013. 700E+O0o.1.063E 020.

4.2SOE-01 3.280E-01

o.3.080E-015.092E 00

R8; 08

2.WOE-021.537E 020.

0.4.688E 011.5G3E 013. 8SOE-02

o.0.0.2.31OE-O2

0.0.4.424E 001.5WE m2; 690E-03

3.71OE-O1o.0.1.DODE 00

0:4. 400E-02o.0.0.0.1.O1OE-O1o.2.331E 010.

7. oooE-022. 7mE+ooo.0.0.3. 000E-021. 669E+O0o.3.404E 020.

3.71OE-O1

o.0.0.0.

RH109

o.0.0.8. 000E-01 1.OooE-ol

o.I .000E-012.474E 010.

0.0.1.414E 01

PD109

o.0.0.

PD111

&o.

PD112

0.0.

&i 09M

o.0.0.

mlllm

o.0.0.

QGI 11

2.500E-021.004E 030.

RG112

0.8.143E 01

F&13

1.5mE-ol7.746E 01

a;i14

o.1.105E 00

Ailsrn

::

Ails

1.90DE-027.803E 00

di13rn

o.0.0.

2.31OE-O2 1. 430E-OS o. 3. oom-021.000E-03 1.67U+O0o.2.S03E 02 ‘?:662E 030.0. 1. 900E-021.ODOE-02 ::OOOE-O1o.1.68SE 01 ~.093E 020. .

3.600E-01 o.

0.0.2.349E 03 %54% 030. 3.128E 021.WOE 00 5.260E-04

o.006.263E 018. 490E-01

o.0.4.539E m

o.

0.0.1.581E 020.

0.1.698E 022.124E 019. 160E-06

o.9.341E 021.13SE 021.730E-02

1.000E 00 0.1.lWE-02’o.9.129E 010.0.6.71OE-O7o.0.0.0.0.0.0.0.

7.900E-02 o.

0.0.8.I02E 020.1.430E-05

o.0.2.192E 010.3: 000E-02

1. 670E+mo.0.0.1. 900E-025.000E-01

::0.

8.800E-02

o.0.0.0.0.

0.0.0.

0.0.0.

0.0.0.

6.500E-02

o.

5.260E-04 9.620E-03

o. 0.0. 0.0. 0.9.620E-03 1.070E-06 o. 1.9DOE-02

o. 5. 000E-01o.6.013E 02 ;:336E 040.0. lpmo:-:;o.1.380E-01 1:070E-017.256E 01 $.558E 030.0. 1:600E-025.660E-04 ~:lWE-O1005.428E 01 &466E 030.0. 1: 4~-022.390E-03 3.900E-020.7.92SE-01 ;:112E 010.0. 9: 700E-034.--03 :.2SOE-02o.0. 0:0. 0.

3.S90E-01 2.500E-02

o.0.0.2.992E 021.431E 00

0.0.584E 03

0.3.867E 03

0.9.160E-06

0.6.820E-05 6.780E-01

5.900E-022.860E-013.698E 030.8. 2SOE-03

4.800E-025.I08E 020.3.630E-OS

4.000E-02o.7.580E 015.690E-01 4. 930E-01

o.1. 470E-012.121E 030.

1.960E-014.071E 020.1.390E-01

!:4.268E 01

4.81~-03 2.019E m 5.S60E-01

o.5.560E-013.OSSE 010.1. 540E-02

o.S.992E 000.3.460E-02

o.0.6. 426E-014.170E-01 4. 320E-01

o.4.320E-01o.0.3.460E-02

o.2.117E 020.

0.0.0.5.SOOE-04

o.0.0.1.207E 000.

4. mtx-03o.S.S08E 000.0.1. 120E-06o.0.0.

7. 700E-034. 2saI-02o.1.466E 020.1. 6WE-021.1OOE-O10.0.0.

1.900E-02

o.?I:149E 010.1. S70E-09

o.0.4.462E m1.81OE-O13.630E-05

o.0.0.

0.

0.0.0.0.

0.0.0.

21

-NUCLIW -LR1’lBC411 -L~DR2 -’f235T~l >-V235THc2J-EcBETRJ -Ec~MM~J-V239FIX 1 )-V239FRC2>

-EGC 1> -EGC2) -EGC3) -EGC4> -EGC5> -EGCG> -EGC7>

-BONE -G. I. -KIDNW -LIUER -LUNG -MUSCLE-PRNCRERS -PROSTIITE -SPLEEN -TESTIS -THVROID -WOLEBWV

CD1lSM 5.500E-04 1.e70E-07 0.0.0.1.719E 020.&

0:6.460E 030.

7. 000E-043.e20E-03

6. OSOE-01 3.600E-02

o.

.

.

0. 1O.OOOE-O4o. 1.!562E 04

0.c;i 15 5.500E-04

6.000E-02 1.250E-01o. 7.2e3E 030. 0.

3.SOOE-02;.713E 05

3:490E-06

o.0.5.625E 03

0.1.6BGE 050.

1.850E-01

o.

9:700E-039.117E-02008.124E 030.1.IDOE-02e.7ooE-02o.0.

3.180E-01

o.0.2.46SE 023.480E-01

o.9.275E 030.6.G40E-05

2.540E-01o.0.2.31OE-O4

::0.

6.160E-01

o.

ml 17M 1.OSOE-02

;.GOOE-02 O.0.

0: 0.CD117 6.640E-05

o.1.270E-033.060E-01o.0.

0.0.0.8.IOOE-01

o.2.120E-01

o.

6.600E-035.437E-02o.0.0.

0.1.270E-03o.0.0.

0.0.0.

0. 2.120E-01o. 0.0. 0.CD118 1.00N 00 2.31OE-64 O. 1.400E-02 2.670E-01 O.

0.8.230E-03 ~AOOE-02

o.0. 1.021E 02 $7SOE 01 ;:564E 01 j020E 01 &

o.

0. 0. . . . 2.oe7E mIN115N 3.490E-06 4.270E-05 0. 9.70CE-03 1.60DE-02 3.160E-01

3.160E-01 O.8.750E-08 9.SmE-02

7.572E 00~.00t3E 02 &lE~;:i3137EOl !:45GE 02&o.

3.060Em 1.027E01I:i 17fl 2:31OE-O4 1:O1OE-O4 O: 6.600E-03 5.150E-01 1.300E-01

7.300E-06 5.437E-021.020E-01 2.800E-02 o.6.155E 01 :.651E 02 :.p= g &82E 01 %QoE 02 ::

0.

0. . . . 1.4S6E01 1.16~01IN117 6.640E-05 2.570E-04 o.

7.30aE-uo.3.oeoE 010.

5. moE-034.586E-02o.2.7e4E 025.2SOE 001, 400E-02e. 6mE-02o.1.5wE 016.240E-011.400E-020. 6C0E-020.1.134E 024.720E m

2.430E-01 7.260E-01

o.1.61OE-O11.92SE 01

I~i 18

5.650E-014.032E 020.

0.e.770E 014.390E 011.380E-01

o.0.e.3ooE m1.851E m2:31OE-O4

o.2.167E 010.1.050E-03

e.lscwol1.638E 020.

2.440E-01

o.

0.1.leoE-04o.2.572E 000.

0.2.639E 000.

IN1 19

2.440E-CJ1e.32tx 004.170E 006.420E-04

o.0.4.475E-016.050E-01 8.150E-01

o.

0.1, moE-030.1.946E 010.0.1. DOOE-02o.0.0.

0.1.997E 01

I:i21

o.0.3.370E m1.203E m

u.6.3WE 013.lsOE 00

9.400E-01

o.

I.000E 00 2.31OE-O2 2. oom-039. 200E-020.0.0.

0.0.0.

SN119M

o.0.0.6.420E-04

9.400E-01o.0.3.270E-08

o.0.0.0.i : 400E-02

e. 6WE-02o.4.72eE 041.180E02

2.400E-02

o.

0.1.800E-06o.2.717E 020.

0.1.287E 03

s;i21

o.0.5.775E 021.130E-01

o.1.75eE 030.2.310E-02

o.0.0.

0.

0.

7.130E-06 o.1.650E-04o.1.644E 010.0.5. 000E-03o.2.768E 030.

1. SOOE-029.200E-02

o.4.207E 02

Sk 23tl

o.1.493E 03 %o.6.930E-02 &420E-08

o.0.3.921E 015.1 6w-ol

o.1.225E 031.394E 011. 300E-03~.looE-ol

2. 20CE-02

o.&774E 04

Ai 25M

o.1.342E 040.1.000E 00

2. 200E-02o.0.1. 190E-03

o.0.4.070E 037.e90E-ot

u.2.820E OS2.3S1E 03

,

.

0.2. 30CE-02o.0.e27E 020.

3.570E-01

o.3.570E-012.271E 040.

0.2.lmE 040.

0.0.1.963E03

22

-NUCLIDE -LRFBDQ1 -L-2 -V235TNC 1)-V23STNC2)-ECBETR) -ECWU’#lfl)-V239f9C 1)-V239F9C2>

-EGC1> -EQC2) -EGC3> -EGC4> -EQcs) -EQC6> -EQC7>-mm -G. I. -KIDNEV -LIUER -LUNQ -HUSCLE-PllNCRE~ -PROSTRTE -SPLEEN -TESTIS -TWROID -WWLEBODV

SN125 1. DOOE00 8. S40E-07 o.2. 4DCE-02 ! : ~~?2.~-03 2.300E-026.765E-01 S.736E 010. 5. 33SE-01o.2.55aE-ol 4:%2!0. 2.- m1.543E 01 ;.l&tt ::0. .

8. 9mE-ol 8.

0.

-02

00

1y yc&-clf

o:SN127

4. eooE-020.

0.0.l.enx m40300E-01

o.7.41 OE-O5

o.

1.000E 00 2.

0.0.3. 933E 020.

0.1. 657E 030.1.000E 00

0.0.0.

0.2. 030E-04

3:740E 011.430E-01 o.

0. 0.

&2. 590E-01 S. 000E-01

o. 0.0.0.8.1 OOE-O2 4.51 OE-O1

o.&4.664E 037.370E-01 1.775E 00

0.::1.174E 023.71OE-O1 5.340E-01

o. 0.

%022E 023.460E-01 2.635E 00

1.1OOE-O1 1.11OE-O1o.0.1.199E 00 5.350E-01

o. 0.0.3.180E 016.340E-01 7.380E-01

o-“ o.

sN12e 0.4.040E-01 ::

700E-61eloE-ol

0.--0:0.0. &

::0.

SN130

o.0.

2;2s

o.0.0.

0.0.0.4.440E-031.000E 00 0. 2iooa 00

!5.33W-01 :.WOE-010. .S.000E-01

::0. 540E-07

o.0.0.B.140E-09

0. 0.0.e.000E-03 hoE-022.1OOE-O3 ~:670E-010.4.090E-01

1.216E 040.1.000E-13

o.0.0.

2;157E 02 ~:j~~ ~~o.0. 10: omE-041.390E-02 ;.f3ME-01o.5.897E 00 3:744E 03

4.627E 00& 1.300E-016.lSOE-02 4.290E-01

6.420E-07

o. 1.773E 001.394E 02 ;.399E 030. .

0.0.0.2.170E-06SB127 7.41OE-OS

4.330E-011.474E 040.2.03U-04

o.0.0.2.O1OE-O5

0.2.376E 042.703E 01

;“E$:2:190E-01o.0.

8.7SOE-01o.

S;i 28

6.S90E-01o.0.2. 030E-04

4.390E-01o.0.1.160E-03 o.

0.0.2.629E 000.1.DooE-ol5. 920E-01o.8.135E mo.

3:600E-014. 680E-01o.l*OIX 033.315E 008.00DE-011.129E+O0o.3.144E 039.96W 00

1.600E-011.118E02o.

3. 75a-ol1.462S 030.

S8129 1. 070E-04 4.1 eoE-05

o.3.472E 02

di30

7.380E-01 o.4.549E 03 0.0. 0.

1.630E-03&911E 011.198E m

o.

4.440E-03 o.1.409E+m t%%%l.moEmo.6.079E-01 ;.:~~ ~3o.l.mtx m 2:600E 00~.w3E+oo ~.203E+oo

2.

0.

650E

020E

600E

460E

00

00

00

00

0.2.467E 010.

8.500E-013.232E 020.3.4WE-03

o.0.$02CE-04

o.7.022E m8.51OE-O1SB131 1.

0.0.3.3B4E 01

S; i 32

0.4.416E 020.

1.020E mo.0.5. 500E-03

&9.046E m

S. 250E-03 2.149E m 1.

0.0.0.

$i33

::0.l.moE 00

1.s56E m0.0.2.820E-03

4.400E-020.

0. 0.-.0.7.81OE-O1

2.300E m

o. 4.000E 001.164E+O0 ;.~~~0.1.887E-01 ;:2t#j;

:: l:moE 005.170E-01 ;:230E-01o.

0.:: 0.

2.

0.~:O03E 000.

SE134

o.0.0.

001.04GE 020.I.000E 00

0.0.0.1.440E-02

o.2.292E m2.200E m o.

0.0.0.0.

0.

::

0.

;:

23

-NUCLIDE -LRIIB091 -L=2 -V235THC 1)-V235THC2>-ECBETR> --V239FRC1 )-V239FRC2)

-EQC2) -EGC3) -EGC4) -EGC5> -EGC6> .

-(3.1. -KIONIW -LIVER +H -FWCLE

-PROSTRTE -SPLEEN -TESTIS -THVROID -WHOLEBOW

-ECGN’U19)

-EGC7>-EGC 1>-BONE-PRNCRERS

TE125M 1. 450E-01

o.

8.140E-09 1.300E-07 O. 6.000E-03 0.

0.7.000E-06 $771E-02o.

;.413E 03 & 7.669E 02 3:204E 04 &9.956E 02 1.e97E 02 4.357E 02

2h70E-06?:640E-08 9.OWE-03 3.5WE-02 4.000E-031.2B4E-03 $708E-02

o.1.2G6E 03 ~:

o.3.712E 02 2:184E 04 %

o. 4.207E02 7.5S6E 01 2.460E 022.170E-06 2:070E-05 ~. 1.040E-01 2.240E-01

. 3. 432E-01

.

1.1OOE-O11.360E 02

T& 27tl 8.800E-02

o.~:075E 01

TE; 27R 3. 000E-03

o.3. 000E-031.109E 020.

-.0.1.159E03 &

o.7.294E 01 hu 02 ::

0. 3.690E02 1.20W023.506E017.640E-08 ~;070E-OS O. &3$; 2.240E-01

0.3. 000E-03

o.

TE127B

3.000E-031.109E 020.

TE129M

o.1.159E 030.4.180E-05

o.0.0.2. 430E-07

o.0.0.1.720E-04

1.lWE-02o.0.1. 720E-04

1.1OOE-O2o.0.6.690E-06

4.S40E-01o.0.4.620E-04

1.51OE-O1o.0.4.G20E-04

1.51OE-O1o.0.

0.7.294E 013.690E 02

0.8.04= 021.200E 02

0.0.3.506E 01

3.SOOE-015. 290E-01o.1.301E 047.037E 014.SOOE-01Q.7WE-01

3. OouE-cn o.

0.

0.3. souI-02o.3.0S6E 023.454E 02

0.0.2.317E 024.920E-01

o.4.9eeE 01

T;i 29R

o.1.462E 030.4.leoE-05 1.350E-01

o.

0.3. 500E-02o*3.eetE 011.SOSE 02

0.2.1OOE-O2 1.020E-014.300E 01 &4BOE 020. .

5:880E 025.215E 013. Sow-olS.290E-01

o*2.614E 024.920E-01 1.350E-01

o.

TE129B 2.430E-07 :..

2.1OOE-O2$300E 01

TE;31M

1.020E-01e.4eoE 020.5.020E-04

o.0.2.614E 02

0.3.eelE 011.S05E 025. 000E-021.132E+O04.1OUE-O23.769E 024.309E 00

1.54eE m

o.

1. e20E-ol

1.100E-02o.4.005E 027.320E-01

1.060E-016.203E 010.

TE131R

e.3eoE-ol1.147E 040.5.020E-04 3.960E-01

o.

0.0.

1.160E-011.374E 010.

TE131B

1.21OE-O11.e52E 020.6.690E-OG

o.0.5.73eE 007.320E-01

o.1.014E 014.657E 010.

0.1.2e3E 021.504E 01e. eooE-02~.925E-01

3.960E-01

o.0.0.1.014E 014.657E 01

1.160E-011.374E 010.

1.210E-011.e52E 020.

0.IJ.1.2e3E 021.504E 01

0.5.73eE 00

TE132 5. 500E-03 2. 470E-06 I.oerxm2.344E+O0o.2.981E 029.742E 022.020E m2.6SOE+O0o.3*9mE 004.SOOE 006.~-017. e70E-olo.1.os6Em3.861E m

4.360E 004. 236E+O0o.5.664E 032.B61E 024.900E m3.513E+O0o.9.S52E 012.2mE m

Hz%%o.1.704E 011.361E m

6.1OOE-O2 2. 850E-01

o.2.330E-012.G73E 020.

0.4.000E 030.2. 820E-03

o.0.0.2.160E-04

o.0.2.137E 024. 940E-01TE133N 1,630E 00

0.4. 300E-026.412E-01

T:i 33R

9.S70E-011.360E 020.2.820E-03

6.~-01o.0.5. 7WE-03

o.0.4.260E W9. 640E-01 6.620E-01

o.3.310E-01l.lmEmo.

0.0.0.

0.0.7.S75E-01

TE1336 2.18W-04 5.76C41-03 o.0.

6.4WE-01 9.640E-01 6.620E-014.S67E-01o.1.704E01 &

o.

1.361E m 7.57SE-01pwg 4.330E-01 1.900E-01

0:4.200E 02 ::

0.

6.52SE 01 1.67SE 01

3.31OE-O1 3.31~-01 O.1.1OOE 00 $457E01 o.

T:i 34 1:440E-02 ;:750E-04

o.1.os6Em3.681E W5.1OOE m:. 457E+O0

.

1.760E-01 O.;.ee9E 01 g.079E 02 %

. . 0.&e55E011.963E 02

24

-NUCLIDE -L-l -L-2 -V23STNC1)-v23sTl’K2)-EceETa> -EComf’m)-V239FM 1)-V239FRC2)

-EQ( 1> -EGC2) -EOC3> -Eac4> -EMS) -EGC6> -EQC7>-BOW -G. I. -KIIBUEV -LIUER -LLU’iQ -twcLE-PRf’CRE9S -PROSTRTE -SPLEEN -TESTIS -THVROIO -UIFULE_

TE135 1.000E 00 9. 2SOE-03 o.2. 474E+O0o.0.0.

2.690E m2. G34E+O0o.0.0.8.000E-011. 234E+O0o.2. e32E 049.660E OS2.300E 002.1 GSE+OOo.2. e32E 049.660E 0s403BOE m4. S47E+O02. 30tXE-021. 474E 033.e70E 044.26CE m4. 090E+mo.6.240E 032.51OE 0s2.360E m1. s90E+mo.6.240E 032.51OE 0s7.BOOE mG.301E+O0o.4.4S2E 021.s4= 046.1OOE m6. 29eE+mo.2.B6BE 036.70SE 043.1OOE m5.1 97E+m9. 600E-020.0.2.660E 003. 243E+m000.0.1.460E 001.291 E+OOo.0.0.2.6mE 003.31OE-O1o.0.0.

1.SOOE m 0.0.0.

0.

Ik

3.leoE-ol0.0.

0.0.0.6.690E-06

o.0.0.

0.0.o*l.eooE-ol9.900E-07 4.smE-ol

6. 4~-02o.0.0.0.0.0.0.0.

3.960E-01

o.7* BOOE-029.9esE 030.4.620E-04

o.0.0.9. 9mE-07

o.0.2.550E 03l.eooE-ol1131B 3. 960E-01

o.3.leoE-olo.0.

1132

7.emE-029.9e5E 030.2.470E-06

o.0.0.

0.0.2.550E 035.170E-01e.370E-05 o.

3.11OE-O12.eooE-02o.o*

2.192E 00

0.3.000E-03o.0.

1133Q

1.71OE 00 4.2eoE-ol2.136E 03 0.0. 0.

0.0.1.320E 024.31 OE-O12.letx-04 9. 260E-06

o.0.0.

0.1.036E+O0o.0.0.

5.150E-01

o.0.

!:5. 150E-01e.245E 03

:: 7SOE-03

o.0.5.572E 02

1133B 9.260E-06 4.31 OE-O1 5.1 SOE-01

o.5. lSOE-01e.24sE 030.

0.0.0.

0.0.5.57X 026. 640E-012.7SOE-04 2.1 BOE-04 9. m-ol

2.321E+O02.41OE-O1o.0.3.41oE m3. 664E+O05. 470E-01o*o.

2.422E 00

0.3.200E-02o.0.

1.777E m6.439E 020.

3.720E-01o.0.2. e70E-05

0.0.3.97SE 013.160E-011135 e.25ceo3 1.623E 00

0.0.

R1136

2.e70E-ol4.152E 030.1.000E 00

7. e90E-olo.0.e.350E-03

o.0.2.5(3SE 02

0.4. 140E+m9. 600E-02o.0.0.2. 97SE+O0o.0.0.0.1.252E+mo.0.0.0.3.270E-01o.0.0.

1.S46E m

4.4SOE-01

2.736E 00

6.760E-019.eooE-02o.

I ?;7

2.1OOE-O2o.0.I.000E 00

1.304E mo.0.2. e90E-02

o.0.1.400E m 3.900E-01

o.3.900E-01o.0.

0.0.0.I.000E 00

0.0.0.1.160E-01

0.0.0.e.ootx-olI13e o.

0.0.0.0.

1139

0.0.0.I.000E 00

0.0.0.

0.0.0.

3.470E-01 e.omE-ol o.

0.o.0.0.

0.0.0.

0.0.0.

XE133M

2.330E-01

9.260E-06 3.490E-06 o.1.3eoE-02o.

&o.1. 3BOE-02o.0.0.

1:590E-011.499E-01o.2.74eE 030.

0.

0.0.0.

2.330E-01

o.0.2.419E 030.9. 260E-06

o.

%1*51OE-O6

o.

X:l 33 6.620E ms. 560E+O0o.6.e40E 030.

l.omE-ol

o.0.0.0.

0.0.0.

e.looE-02

o.3.000E-03o.

X& 35M

k364E 030.2.e70E-05

to.7. 230E-04 o.

0.

&o.

5. 280E-01

o.s.2eoE-ol0.0.

0.4.44eE 010.

0.0.0.

&oe4E 010.

-NUCLIOE -LR1’lBDal -LRm0Q2 -V235THC 1>-Y23STHC2>-ECEETR) -ECGRNMR)-V239FQC 1>-V239FQC2)-EGC4> -EGC5) -EGC6) -EGC7)-LIUER -LUNQ -MUSCLE-TESTIS -THVROID -UHOLEBOOV

-EGC 1> -EGC2> -EGC3>-BONE -G. I. -KIOtW-PN!CRERS -PROSTRTE -SPLEEN

XE135 2.870E-OS 2.120E-05 2.000E-01 G.300E 00 3.040E-01 2.41OE-O15.4SOE-01 &e43E+ooo.

I:051E03 ~:o.

0.0. 0.3.450Em6.000Em 1:476E m o.3.253E+O0 &496E+O00.

3:94BE 01 &o.

0.0. 0. 0.4.030E 00 S.490E 00 8.GGOE-01 9.000E-013.677E+O0 4.96SE+O03.SOOE-01 o.

1.376E 02 &o.

0.0. 0. 0.0. 5.400E m 1.737E m 9.500E-012.656E+O0 $987E+O00. 0. 0.

.

.

2.230E-01 1.WOE-02 0.0. 1.51eE 030.0. 0. 0.

XE137 2.890E-02 2.960E-03

o. 0.0. 5.G91E 01 &

o. 0.x;i 38 1.160E-01 6.790E-04

o. 5.3mE-ol 0.0. 2.274E 02 0.

0. 0.x;i 39 3.470E-01 1.690E-02

9.500E-01 O.0.

0.0. 0.

0. 0. 0.5: 0: 0.0. 0. 0.

XE140

0.

1.000E 00

0.0.

4.330E-02

o.0.0.6.170E-07

o.1.384E+O0o.0.0.0.8.300E-02o.e.970E 030.

3.eooE 001. 443E+O0

1.320E 00 0.

0.0.0.0.1.070E-01

o.0.0.

CS136

o.0.0.

1.000E 00 2.oeeE 00

0.

3~emE-ole.3mE-02o.6.745E 040.

0.5.701E 035.629E 031.71OE-O1

2.960E-011.780E 030.

Csl 37

e.3mE-ol1.S95E 040.2.960E-03

1.1 9EO031.0 GE 04

s.9esE 037.320E-10 o.

0.

1.500E-013.510E-01o.3.813E 04

6.150E 006.847E+O0o.1.969E 050.

0.1.911E 041.031E 041.099E m

o.2.866E 04

2138

0.4.987E 030.6. 790E-04

o.2.895E 043.358E 043.61OE-O4

2. 49uE-ol1.340E 02G.70SE 011. 220E-03

o.2.SOOE-011.103E+Wl.-me.9e3E 010.1.070E m2.14SE+O00.2.331E 01

CS140 4.330E-02 1.OSOE-02%OOEO0 6.WOEm 1.949Em 1.400E 00

0.2.98BE+W $431E+O0

4.00(JE-01 pmE m o.0. 0.

0. 0.($

o.0:

0.0.

0. . 0. 0.

s;740E m6.071E+CM3o.4.831E 020.6.470E 005.1 32E+O00.;.072E 01

.

2.12SE 00

2.S1OE-O17. OWE-033.252E 01

~i39

1.9SOE-016.98(3E 020.1. 690E-02

3. 940E-013.e96E 014.318E 011.601E m 2. 320E-01

o.0. 2.~-02 2.070E-011.134E 01 J.31OE 023.780E 010. . 1.- 01

0.7.S7SE me.lo7E m

CS142 i:oooE 00 3:O1OE-O1 0: 3i200Em2.423Em 1.4ooE m

o.1.es6E+m &.%7E+oo

4.moE-ol ~.moE m o.0. 0.

0. 0.● o. 0; o.

0.B:i 37M

o.7.32OE-10 ::440E-03 :: 5.BSOE 00 ::

3.00CE-03 p3eE+oo6.300E-01

o. 6.3WE-01 O.2.502E-01 ;.362E 00 3.230E-03 k330E-03 6:511E 00 &OE~

o.

1.61SE-03 2.704E-Ot 0.B;i 39 1:220E-03 1.360E-04 8.~-02 6.SSOE m 9:1OOE-O1 5.000E-02

4.600E-02 O.1.670E-01 5.29%E+O0

3.130E 02 ;.176E 02 $!:377E-01 t~$? %961E 02 t138E-01o.

0. 3.194E-01 1.161E 020. 1.622E 01w140 l:OSOE-02 6.170E-07 3.SOOE-01 6.3= 00 2.790E-01 2.190E-01

6.S60E-01 ~.oeeE+oo1.400E-02 1.640E-01 O.2.142E 04 ;.150E 04 2.381E 01 $!:331E 01 4:BOOE 04 ?:209E 01

0.

1.S03E 01 2.907E 03 0.B:i41 “

1.453E 032.770E-02 6.420E-04 1.700E 00 6.300E 00 1.143E 00 1.740E-01

1.060E-01 6.8WE-02 o.1.770E+o0 g:2soE+m

9.606E 01 ;.726E 02 1.827E-01 %686E-02 1.199E 02 &~~-C&o.

0. , 1.271E-01 1.S89E02 O. .

.

.

26

-NUCLIOE -Lam8ml -LM80Q2 -v23sTtK 1>V23STHC2)-EC*TR> -EComt’111)-V239fQC 1)-V239FRC2)

-EGC1> -EGC2> +0(3) -EQC4> -EMS) -EGCG>-BoNE

-EQC7>-a. I. -KIH -LIVER -LUMG -MUSCLE

-PRMRERS -PROST9TE -SPLEEN -TESTIS -THVROID -nl’KILEBoovBR142 3. O1OE-O1 1.OSOE-03 2.2ouE 00

2. 9S4E+O03.1 GOE-012. 524E-029.31OE 000.2. 894E+mo.0.0.0.1. 240E-021.457E m1. 740E 030.1.000E-019. 9SOE-02o.2. 273E 020.5.moE-ol4.730E-011.OmE-ol9.427E 010.

5. 400E 004. 920E+O0o.3.132E 010.

5. 670E-01 7. 720E-01

o.3.1OOE-O22.514E 01

B% 43

0. 4.170E-014.S18E 01 4.777E-02o. 2.388E-021.000E 00 5.770E-02

o. 0.0.

0.0. 0,0.

L;i40 6.170E-07 &E-06

5.330E-01 3.SOOE-022.923E 04 ~.o. .

0.7.170E-031.020E 001.17wm4.470E 00

3. 578E+O0o.0.

0.

0.0.0.0.4. e30E-ol

o.6.3SOE 005. 100E+OO

2.468E 00

1.170E-011.850E-013.657E 030.

~.410E-olo.2.807E 040.

LJ.e.44sE 029. smE-olL9141 6.420E-04 5.06W-OS 6.400Em

5. 3SOE+O0o.1.268E 030.

2.700E-02

o.0.5.065E 02

L;i 42

0. 2.70M-021.834E 03 0.0.1.OSOE-03 ?:360E-04

o.0.3.800E 011*942E m 1.438E 00

2.240E-01

5.900E mS.394E~2. 220E-01&14eE 02

6:OOOE 00f. 849E+O0

o.1.838E 020.

3.30m-01 7.400E-020.003E 02 ;.0.5.770E-02 8:2SOE-04

4. 880E-01o.1.e29E 011.375E m

0.o*4.147E m1. 4SOE-01

LR143 i:s30E 001. 270E+mo.2.S61E 010.0.4. 240E-04o.1.407E 040.0.5.120E-02o.1.693E 030.0.2.460E-01o.3.319E 040.0.6.91OE-O1o.5.750E 00

::1. 202E+O0o.9.687E mo.3. ooaE-021. S30E-04o.8.997E 030.0.2.31~-03~. $n0#3f

0:0.1. 990E-02o.3.314E 020.0.1.O1OE-O13.160E-01:.43SE 01

.

8.41OE-O1

o.6.200E-025.770E 01

Gi41

3.81OE-O1 3.98UE-012.O1OE 02 0.0. o*S.06E-OS 2.430E-07

~:392E 02u.

G:400E 005. 3soE+mo.4.764E 04

1.020E-01

o.1.020E-011.370E 04

~i43

o.5.48BE 03 ~:2E19E 040.8.2SOE-04 5:830E-06

o.0.1.699E 033.71OE-O1

o.6.- m4. 900E+O0

3.790E-01

o.1.660E-011.391E 030.

1.360E-01 7.700E-028.098E 03 ;.447E 030.1.000E 00 2:830E-08

o.0.2.107E 02

0.7.024E 030.

CE144 S.620E 004.298E+O0o.6.651E 04

8.1OOE-O2 3.400E-02

o.1.700E-02!5.417E 040.

CE145

o.2.344E 03 &Q5E 040.1.000E 00 3:8SOE-03

o.0.4.462E 035.120E-01

o.3.980E 003.530E+O0

9.000E-01

o.0.5.898E 00

;i 46

0. 9.000E-011.884E 01 ;.230E 000.1.000E 00 8:2SOE-04

o.0.5.600E-012.2s02-01

o.1.884E 01

&070E m2. 748E+O0o.4.728E 010.

3.000E-01

o.2.430E-016.S2SE 000.

PR143

o.6.804E 01 $91OE 000.5.830E-06 5:81OE-O7

o.o*1.407E m

:.o~+fi 3.1 SOE-01 o.

0:3.415E 04 %

o.

0. 1.112E03

o.1.571E 04

0.7.737E 03 ~:038E 04

0.PR144

o. 0.2.830E-08 6.7--04 5:6= 00

4.300E+O01.1 mE-021.219E 02

1.207E m 2.900E-02

o.0.0.3.642E m6.820E-01

o.5.OSOE 010.

PR1450.3.980E 003. Ss&+mo.1.3SOE 030.

0.

0.3.S5=-03 3.21OE-OS

! ~:954E 03 $757E 01

8:2SOE-04 4.620E-04

o.0.4.050E 011.272E m

o.5.63SE 02

Pii 46 1.075E 00

0.

3.070E m2.849E+O0o.2.776E 020.

0.0.8.250E m

o. 7.590E-01 0.7.660E 01 $:m7E 02 ;.840E 010. .

27

-NUCLIDE -LRM8DQ1 -LfH’BDQ2 -’f235THCl )-V235TtK2)-ECBETFl> -ECGQMI’%1)-V239fQC1 )-V239FRC2)

-EGC1> -EGC2) -EGC3> -EGC4> -EQC5) -EGC6> -EGC7)-BONE -G. I. -KIDNEV -LIUER -LUNG -MKCLE-PRNCRERS -PROSTl?TE -SPLEEN -TESTIS -TNVROID -UH&EBCMIV

ND147 1. OWE 00

1. 150E-019.700E 030.

7. 280E-07 0.6. 440E-03o.G.802E 030.0.1. 3BOE-01o.0.0.0.f. g:g-o;

2: 325E-01o.0.9.330E-06o.1.701E 040.0.2. 000E-03o.6.307E 020.

2.360E m2. 250E+O0o.3.654E 040.1.130EO01. 42SE+O0o.0.0.4. 400E-018.330E-011.O1OE-O11.333E 020.2.360E 002. 250E+O0o.6.353E 040.1.13wm1● 430E+O00.1.033E 040.4.400E-018. 890E-01o.6.767E 030.4.4om-ollpoOE-ol

4:332E 040.1.500E-014. BOOE-olo.4.500E 030.3. 300E-022.540E-01o.1.231E 020.

2.2eoE-ol 1.960E-01

o.

I

.

8.000E-039.621E 03

N;i 49

0.7.669E 030.

0.0.1.170E 03

4.060E-01

o.

1.000E 00 1.070E-04 4.320E-01

2.730E-01o.0.

ND151

7.300E-02o.0.1.000E 00

&&620E-04

o.0.0.6.290E-01 6.780E-01

o.6.600E-022.840E 010.

PM147

1.440E-011.928E 020.7.280E-07

2.140E-012. 400E-01o.8.450E-09

0.0.4.000E m6.200E-02

o.0.

Y61oE-o1

0.

0.0.1.264E 05

P%l 49

0.1.788E 030.1. 070E-04

~:425E 040.3. 570E-06 7.OWE-03

o.7.000E-032.643E 030.

PM151

o.9.173E 020.9. 620E-04

2. 890E-01e.259E 030.7. 000E-06

o.2.271E 030.7. WOE-06

o.0.0.

7.150E-01

o.

0.5. 650E-02o*3.771E 020.0.s. 780E-04o.2.063E 040.

3.81 OE-O1

4.260E-011.438E 030.

0.1.325E 030.2.36OE-10

0.($

1:900E-02sll151 o.

0.0.1.184E 05o*

Srll 53

0.1.087E 030.1.000E 00

0.6.449E 040.4.1OOE-O6

o.I.1OOE 03

i: 820E-04

o.2.850E-01o.

0.0.6.937E 032.230E-01 1.070E-01

o.

0.1.920E-02o.3.2S6E 010.

9.400E-021.364E 03

di55

o.4.321E 03

0.0.1.3S7E 026. 080E-01

o.1.000E 00

0.1.770E 020.

1.150E-01

o.

0.9.500E-02o.3.386E 020.

1.150E-013.456E 010.

0.0.3.675S 00

Sfl156 1.000E 00 1.920E-05 0. 1.300E-02 3.000E-01 o.1.020E-01 ;.61OE-O1

o. 0.4.04!E 02 ~:589E 03 ~:076E 02 ;:094E 04 $104E 03 0.

0.

E:i553.300E 01

4:820E-04 1:290E-08 0; 3:300E-02 5.700E-02 6.400E-026.000E-03 2.600E-01

6.400E-02 O.7.727E 04 ;.530E 03 ~:109E 05 ;:094E 04 ~:488E 04 &

o.

0. . . . . 7.886E 03EU156 1.920E-05 5.35OE-O71O.OOOE-O4 1.400E-02 4.230E-01 O.

0.1.900E-02 ;.800E-01

2.438E 04 ;:704E 04 ;:633E 04 ;:679E 04 ;:314E 05 &o.

E:i57. 4.307E 03

l:OOOE 00 1:2SOE-05 0; 7.BOOE-03 4.130E-01 4.500E-01

o.3.500E-02 1.180E-01

4.500E-01 O.9.099E 02 ;.022E 03 ;.328E 03 ~:071E 03 ~:034E 03 &

o.

0. . . . . 1.505E 02EU158 1.000EOO 1.920E-040. 2.~-03 1.037E 00 0.

0.3.7WE-02 &700E-02

1.357E 02 $235E 02 ‘@4E 02 ~:109E 02 ~:620E 02 &o.

0. . . . ● 1.075E 01

.

.

28

-NUCLIOE -IAW191 —mIBm2 -v23sTHC 1)-V23STHC2>ECBETQ) -ECGM’tQ)-V239FRC 1)-V239FQC2)

-EG< 1> -EGC2> -EGC3) -EGC4> -EGC5) -EGC6> -EGC7>-Bow -G. I. -HONEY -LIUER -LUNQ -f’USCLE-PRNCRHIS -PROSTRTE -SPLEEN -TESTIS -THVROID -UHamow

G0159 50780s-04 1.070E-OS o. 10. OOOE-O4 2.940E-01 5.700E-021.000E-02 poE-02

&700E-02 O. 0.3.OISE 03 & 2.213E 03 %

o.0.

0: 0. 0. 0. 0. 0.V91 .1980E-04 .131W-06 .0 5.81 ,593 . m4

o.. m2 &6

.0042.27 E 05 ~:49 E 04 0.

0.1.97 EOS&

o.

0.0.

. 0. 0. 0. 8.63 E 03

29

APPENDIX C

FPIC/U-Pu CODE OPERATING INSTRUCTIONS

A

LAST

KEY

The data input to the code are as follows:

Data Block 1 - Nuclide decay data and235

U thermal-fission yields.

Data Block 2 - Body-organ dose conversion factora.

Data Block 3 -239

Pu fast-fission yields.

Data blocks for 201 nuclides are supplied with thecode package. The input to be supplied by the useris as follows:

Card A (1216 format)

NODOSE Number of shutdown times. Maximumof 55. If NODOSE = 51, the programwill supply 51 shutdown times rang-ing from 10 to 2.0E+09 sec.

= O, another case follows.= 1, no more cases to be read.

= O, no individual nuclide dose

data requested.= 1, calculate dose data for select-

ed nuclidea (see Card B).= -1, calculate dose data for all

nuclides.

Card B (1216 format) Required if XEY - 1.

Iwo Number of nuclides for which dosedata is requested.

NUCNO (I) Nuclide identification numbers.

I=I,NNO See code lieting for theee numbers.Nuclide numbers must be in aecend-ing order.

Card C (6E12.5 format) Omit if NODOSE = 51.

RETIME,I = 1, NODOSE Shutdown times in sec.

Card D (6E12.5 format)

XLPCY1 Period of(see) .

XLPCY2 Number of

XNPCY1 Period of

XNPCY2 Number of

(See Fig. 4)

short operating cycle

short perioda.

long operating cycle (see).

long periods.

For noncyclic operation, all numbers on Card Dshould be input as 1.0.

Card E (6E12.5 format)

POWER Operating power (W).

OPTIME Duration of constant power operation(aec).

Card F (1216 format)

JJ

NPUN

--r

= 1, Decay powers computed for235U

thermal and 239PU faat fiaaion.. 2, for 239Pu fast fission.= 3, for 23%J thermal fission.

= O, cards will be punched, one perahutdowo time, in 6E12.5 formataa follows:

OPTIMR (see)POWER (W)Shutdown time (see).Beta decay power (MeV/aec)Ganma decay power (MeV/see)Total decay power (HeV/see)

= 1, no punched output.

OPTIME

1s:LPCY1

L1--_llFig. 4. Schematic of cyclic operation.

I30