XA9846775 International Atomic Energy Agency XNDC(NDS)-376 D i s t r . : G+SQ 1 N DC INTERNATIONAL NUCLEAR DATA COMMITTEE HANDBOOK OF NUCLEAR DATA FOR SAFEGUARDS N. Kocherov, M. Lammer, O. Schwerer Nuclear Data Section International Atomic Energy Agency Vienna, Austria December 1997 IAEA NUCLEAR DATA SECTION, WAGRAMERSTRASSE 5, A-1400 VIENNA 15
This document is posted to help you gain knowledge. Please leave a comment to let me know what you think about it! Share it to your friends and learn new things together.
Transcript
XA9846775
International Atomic Energy AgencyXNDC(NDS)-376D i s t r . : G+SQ
1 N DC INTERNATIONAL NUCLEAR DATA COMMITTEE
HANDBOOK
OF
NUCLEAR DATA FOR SAFEGUARDS
N. Kocherov, M. Lammer, O. Schwerer
Nuclear Data SectionInternational Atomic Energy Agency
Vienna, Austria
December 1997
IAEA NUCLEAR DATA SECTION, WAGRAMERSTRASSE 5, A-1400 VIENNA
15
Printed by the IAEA in ViennaFebruary 1998
INDC(NDS)-376D i s t r . : G+SQ
HANDBOOK
OF
NUCLEAR DATA FOR SAFEGUARDS
N. Kocherov, M. Lanimer, O. Schwerer
Nuclear Data SectionInternational Atomic Energy Agency
Vienna, Austria
December 1997
- 2 -
ABSTRACT
This handbook contains nuclear data needed by safeguards users for theirwork. It was initiated by an IAEA Working Group. The contents were definedby the replies to a questionnaire sent to safeguards specialists, andrestricted by the availability of evaluated nuclear data. This revisededition was updated after review of the preliminary issue by safeguards andnuclear data experts and when updates of nuclear data libraries were released.
The handbook contains the following basic nuclear data:
actinides: nuclear decay datathermal neutron cross sections and
resonance integralsprompt neutron datadelayed neutron data
fission products: nuclear datathermal neutron capture cross sections and
resonance integrals
fission product yields
- 3 -
TABLE OF CONTENTS
Abstract . .
Foreword . .
Introduction
Page
2
4
5
Section A
A-lA-2A-3A-4A-5
A-6A-7A-8
Actinide Nuclear Data
Half-lives and decay branching fractions 7Alpha energies and emission probabilities 10Gamma ray energies and emission probabilities 14X-ray energies and intensities 20Thermal neutron cross-sections, resonance integralsand related parameters 25Average number of neutrons emitted per fission (v) . . . . 27Prompt neutron multiplicity distributions P(v) 29Delayed neutron six-group parameters 30
Section B: Fission product nuclear data 32
B-l: Half-lives and decay branching fractions 33B-2: Gamma ray energies and emission probabilities 35B-3: Thermal neutron capture cross sections and
This handbook was initiated by an IAEA working group, and the contentswere defined by the replies to a quiestionnaire sent to safeguards experts,as outlined in the preliminary edition (INDC(NDS)-248, June 1991; see inparticular Appendix A) . The preliminary edition of the handbook wasdistributed to safeguards and nuclear (and other) data specialists for review.
The replies and comments on the preliminary edition received fromexperts did not contain major changes or suggestions for new sources ofnuclear and other data. Therefore we waited with the update of the handbookuntil revisions and updates of the major data files and other sources ofnuclear data became available.
This edition contains no additional tables. The data have been revisedin accordance with suggestions and comments received from experts and thelatest available nuclear data. Again, each set of tables is preceded byexplanations, information on the data selection, the sources of data used andthe availability of complete data files. The Handbook is also available ina PC version, which was used for updating the handbook, and which can beobtained on diskette in a slightly different format from the Nuclear DataSection (see introduction for the address).
Acknowledgement
We would like to thank S. Aung, M.M. Seits and M. O'Connell, who havehelped to produce the preliminary as well as the final version of thehandbook, and G. Pospischil who has written the PC code for the handbook ondiskette.
Contact
Scientists who wish to be included in the distribution list for thishandbook, should contact M. Lammer at the address given below. Then they willalso automatically receive all later revisions and amendments to the handbook.Any mistakes found, comments or suggestions for additions should also becommunicated to this address.
M. LammerNuclear Data SectionInternational Atomic Energy AgencyP.O. Box 100A-1400 Vienna(Austria)
- 5 -
INTRODUCTION
This handbook contains recommended values of nuclear data needed for thedevelopment and application of safeguards nuclear materials accountingtechniques. We have included only those data that were requested bysafeguards users and which were readily available to us. The data given aregrouped in 3 sections: Section A contains decay data, thermal neutron crosssection data, resonance integrals and data on neutron emission in fission foractinide isotopes. Section B contains decay data and thermal neutron crosssection data of fission product nuclides. Section C contains fission productyield data.
We have used the following criteria for selecting the data for thehandbook: When available, we have generally given preference to datarecommended by international committees or working groups. When such datawere not available or superseded by more recent values, generally availabledata files were used. When different values were found in different datafiles, we have given preference to data with uncertainties, or to the mostrecent suitable values. In the case of fission yield data, a group ofspecialists recommended not to give a single "best" data set; considering thedifferent existing views on data evaluation methods in this case, two datasets have been included.
Introductory pages to the data tables give further explanations,arguments for the selection of the recommended values (special remarks aregiven in footnotes), references of the sources of data and information on theavailability of larger or complete data sets that are not included in thehandbook.
Users of this handbook who wish to receive complete data files, caneither request them on magnetic tape or PC diskette from one of the fourregional Nuclear Data Centres, or use their on-line services for directretrieval of some of the data files. Further information can be obtained fromthe Nuclear Data Centres (see their addresses below).
The handbook is also available as a PC version 'SGNucDat' from the IAEANuclear Data Section (see address below) together with guidelines for its use.It can be used to display the data contained in the handbook, and to performdata searches, selections and different sortings, on a PC or laptop.
For USA and Canada:
National Nuclear Data CenterBrookhaven National LaboratoryP.O. Box 5000Upton, N.Y. 11973-5000USAINTERNET: [email protected]
For other OECD countries:
NEA Data BankLe Seine Saint-Germain12 Blvd. des IslesF-92130 Issy-les-MoulineauxFRANCEINTERNET: [email protected]
IAEA Nuclear Data SectionP.O. Box 100A-1400 ViennaAUSTRIAINTERNET: [email protected]
SIEXT PAGE(S)toft BIAUK
- 7 -
SECTION A: ACTINIDE NUCLEAR DATA
A-l: Half-lives and decay branching fractions
Description of table entries:
decay mode: aP-ec
units:
rel err:
smh
alpha decaybeta decayelectron capture
secondminutehour
dy
IT isomeric transitionSF spontaneous fissionT total half-life
dayyear = 365.2422 days
relative la uncertainty (in %)
branching: given for each decay mode (should sum up to 100%)
exponents: read E±n as 10"
Source of data:
The tabulated data have been extracted from a data set recommended byparticipants of an IAEA Co-ordinated Research Programme (CRP). The complete dataset is published in: IAEA Technical Report Series No. 261 (STI/DOC/10/261), pp.154-159 (1986).
The data were revised in October 1997. Updated values of half-lives andbranching ratios were taken from the ENSDF file, revision of May 1997, and thecompilation by R.B. Firestone and V.S.Shirley (Ed.) "Table of Isotopes", 8thedition, New York, J.Wiley & Sons,Inc.,1996.
Table A-l
nuclide
81-T1-208
82-Pb-212
83-Bi-212
86-Rn-220
87-Fr-221
88-Ra-224
88-Ra-225
88-Ra-226
88-Ra-228
89-AC-225
89-AC-227
decaymode
13-
11-
Tafl-
a
a
a
13-
a
15-
a
Ta13-
units
m
h
mmm
s
m
d
d
y
y
d
yyy
half-lifevalue
(3.053
(1.064
(6.055(1.685(9.452
(5.56
(4.9
(3.66
(1.49
(1.600
(5.75
(1.00
(2.177(1.578(2.207
±
±
±
±
+
+
+
+
±
±
0.004)
0.001)
0.006)0.003)0.013)
0.01)
0.2)
0.04)
0.02)
0.007)
0.03)
0.01)
0.003)0.011)0.003)
E + 00
E + 01
E+01E+02E+01
E+01
E+00
E+00
E+01
E+03
E+00
E+01
E+01E+03E+01
rel err
( 0.13)
( 0.09)
( 0.1 )( 0.18)( 0.14)
( 0.18)
( 4.1 )
( 1.1 )
( 1.4 )
( 0.44)
( 0.52)
( 1.0 )
( 0.14)( 0.7 )( 0.14)
branching(percent/decay)
*)
35.9464.06
1.3898.62
± 0.06± 0.06
± 0.01± 0.01
nuclide
89-AC-228
90-Th-228
90-Th-229
90-Th-230
90-Th-231
90-Th-232
90-Th-233
90-Th-234
91-Pa-231
91-Pa-233
91-Pa-234
91-Pa-234m
92-U -232
92-U -233
92-U -234
92-U -235
92-U -235m
92-U -236
92-U -237
92-U -238
92-U -239
93-Np-236
93-Np-236m
93-Np-237
93-Np-239
94-PU-236
decaymode
13-
a
a
aSF
13-
aSF
13-
13-
aSF
13-
13-
13-IT
aSF
aSF
aSF
aSF
IT
aSF
13-
aSF
13-
T13-ec
T13-ec
aSF
13-
aSF
units
h
y
y
yy
h
yy
m
d
yy
d
h
mh
yy
yy
yy
yy
m
yy
d
yy
m
yyy
hhh
yy
d
yy
half-lifevalue
(6.15
(1.912
(7.34
±
±
±
{7.54 ±1.98 E+18
(2.552 ±
(1.405 +>7.8 E+20
(2.23
(2.410
(3.276>2.05 I
(2.697
(6.70
(1.17(1.5
(6.89(8.
±
±
+:+l
±
±
±
(1.592 ±>2.7 E+17
(2.457(1.50
(7.038(1.01
(2.6
(2.342(2.43
(6.75
(4.468(8.2
(2.347
(1.54(1.23(1.76
(2.25(4.69(4.33
±
±
±
±
±
+
±
±
(2.14 ±>1. E+18
(2.355
(2.851(2.081
±
±±
0.02)
0.002)
0.16)
0.03)
0.001)
0.006)
0.01)
0.003)
0.011)7
0.002)
0.05)
0.03)0.2)
0.04)6.)
0.002)
0.003)0.08 )
0.005)2.8)
0.2)
0.003)0.07 )
0.01 )
0.005)0.1)
0.005)
0.06 )0.3)0.03)
0.04)0.13)0.11)
0.01 )
0.004)
0.008)0.6)
E+00
E+00
E+03
E+04
E+01
E+10
E+01
E+01
E+04
E+01
E+00
E+00E+01
E + 01E+13
E+05
E+05E+16
E+08E + 18
E + 01
E+07E + 16
E+00
E+09E + 15
E + 01
E+05E+06E+05
E+01E+01E+01
E+06
E+00
E+00E+09
rel err
( 0.33)
( 0.1 )
( 2.2 )
( 0.4 )
( 0.04)
( 0.43)
( 0.45)
( 0.12)
( 0.34)
( 0.37)
( 0.75)
( 2.6 )(10. )
( 0.72)(80. )
( 0.13)
( 0.12)( 5.6 )
( 0.1 )(30. )
( 7.7 )
( 0.13)( 2.9 )
( 0.15)
( 0.11)( 1-2 )
( 0.21)
(10. )(20. )( 2.4 )
( 1.8 )( 2.8 )( 2.5 )
( 0.47)
( 0.17)
( 3.5 )(20. )
branching(percent/decay)
3.8
<1.8
<1.6
99.840.16
(0.9
<0.59
(1.64
(7.0
(9.64
(5.45
12.587.5
48.52.
E-12
E-09
E-ll
± 0± 0
± 0
E-10
+ 0
± 0
± 0
± 0
± 0.± 0.
± 1± 1.
<2. E-10
(1.37 ± 0.
0404
7)
02)
21)
03)
07)
55
07)
E-10
E-09
E-09
E-08
E-05
E-07
- 9 -
nuclide
94-PU-238
94-PU-239
94-PU-240
94-PU-241
94-PU-242
94-PU-243
94-PU-244
94-PU-245
94-PU-246
95-Am-240
95-Am-241
95-Am-242
95-Am-242m
95-Am-243
96-Cm-242
96-Cm-243
96-Cm-244
98-Cf-252
decaymode
aSF
aSF
aSF
B-a
aSF
B-
aSF
B-
B-
eca
aSF
Tfl-ee
ITaSF
aSF
aSF
TaecSF
aSF
TaSF
units
yy
yy
yy
yy
yy
h
yy
h
d
hy
yy
hhh
yyy
yy
dy
yyyy
yy
yyy
(8(4
CM CO
(6(1
(1(6
(3(6
(4
(8(6
(1
(1
(5(3
(4(1
(1(1(9
(1(3>3
(7(2
(1(7
(2(2(15.
(1(1
(2(2(8
half-lifevalue
.77
.7
.411
.04
.563
.16
.435
.00
.735
.8
.956
.00
.7
.05
.085
.08
.0
.327
.00
.602
.937
.26
1+ 1+ 0.03 )
0.2)
± 0.003)E+15
+1 +1
1+ 1+
1+ 1+
±
i+ i+
±
±
1+ 1+
+1 +1
1+ 1+ 1+
.41 ±
.11 ±
.0 E+12
.370
.0
.629
.05
1+ 1+
1+ 1+
.85 ±
.86 ±
.19 ±37 E+ll
.810
.320
.645
.73
.55
+1 +1
1+ 1+ 1+
0.007)0.04)
0.01)0.05)
0.011)0.1)
0.003)
0.09 )0.3)
0.01)
0.002)
0.03)1.1)
0.005)0.024)
0.002)0.007)0.16)
0.02)0.05)
0.015)0.3)
0.002)0.14)
0.02)0.02)0.15)
0.002)0.007)
0.008)0.01)0.03)
E+01E+10
E + 04
E + 03E + ll
E+01E+05
E+05E+10
E+00
E+07E+10
E+01
E+01
E+01E+03
E+02E+14
E+01E + 01E + 01
E+02E+04
E+03E+13
E+02E+06
E+01E + 01E+04
E+01E+07
E+00E+00E+01
rel
( 0.( 4.
( 0.
( 0.( 3.
( 0.( 0.
( 0.( 1.
( 0.
( 1.( 4.
( 0.
( 0.
( 0.(40.
( o.( 2.
( o.( 0.( I-
( 1.( 1.(40.
( o.(20.
( o.( 2.
( o.( o.(10.
( o.( o.
( o.( o.( 0.
err
34)3 )
12)
11)5 )
7 )83)
29)5 )
06)
1 )5 )
95)
18)
59)
12)1 )
12)36)7 )
4 )6 )
2 )
04)0 )
7 )7 )
11)52)
3 )37)35)
fl.
(3.
(5.
(2.
(5.
99.0.
(1.
(4.
82.1.
99.0.
(3.
(6.
99.0.(5.
(1.
96.3.
branching(percent/decay)
85
0
75
45
54
879121
9
3
773
5414597 E-
7
37
71293
371
908092
±
±
±
±
±
1+ 1+
±
±
+1 +1
9
±
±
+1 +1 +1
+
1+ 1+
0
0
0
0
0
00
0
0
00
00
0
0.
0.0.0.
0.
0.0.
.04) E-07
.8) E-10
.05) E-06
.02) E-03
.06) E-04
.004004
7) E-04
18) E-10
33
00120012
9) E-09
018) E-06
03039) E-09
002) E-04
008008
') Note: 100% decay of Pb-212 to the 6.055 min ground state of Bi-212.
- 10 -
A-2: Alpha radiation energies and emission probabilities
Description of table entries:
The second column gives alpha energies and their errors in keV for thenuclides listed in the first column. The third column gives alpha emissionprobabilities and their uncertainties (lo) in percent per decay.
Source of data:
The tabulated data have been extracted from a data set recommended byparticipants of an IAEA Co-ordinated Research Programme (CRP) on "Decay data of thetransactinium nuclides" (1978-1984). The complete data set is published in IAEATechnical Report Series No 261 (STI/DOC/10/261) , pp.167-170 (1986).
Note: The data were revised and updated in October 1997. The source of new datais the ENSDF file, revision of May 1997.
A-3: Gamma ray energies and emission probabilities
The table does not contain Y~rays from daughter products in equilibrium.
Description of table entries:
The second column gives Y~ray energies and their errors in keV for the nuclideslisted in the first column. The third and fourth columns give Y~ray emissionprobabilities and their uncertainties (la) in percent per decay and relative errors(in %) in brackets ("rel err"). In general, Y~-cays with energies below 50 kev wereomitted, as they are not measured in applied NDA.
Source of data:
For the revision of October 1997, the new data were taken from the ENSDF file,revision of May 1997. Most of the original data (preliminary version) weresuperseded and replaced in the table. The original data were extracted from a dataset recommended by participants of an IAEA Co-ordinated Research Programme (CRP)on "Decay data of the transactinium nuclides", published in the IAEA TechnicalReport Series No 261 (STI/DOC/10/61), pp.162-166, (1986).
First column: the element considered, followed by the type of the X-raytransition. Only K X-rays are included as the energies of other X-rays are too lowto be visible in Y~ray spectra.
The following notation for X-ray transitions is used (e.g. K al = Siegbahnnotation, K-L3 = associated initial - final shell vacancy) :
K alK a2K (il
K-L3K-L,
. K-M2
Group designations:
KKK
P2 . ,P3 . .P4 . .
. . K-N2N3
. . K-M2
. . K-N4N5
KKK
P50P
. . . K-M,M5
. . . K-0 20 3
. . . K-P2P3
K pi' = K PI + K P3 + K P5K P2' = K p2 + K P4 + K O + K P
The energies of individual X-rays and mean energies of groups are given incolumn 2.
The X-ray intensities per 100 K-shell vacancies are given in column 3. TheX-ray intensities per 100 decays of the nuclide given are listed in columns 4 to6, where the following notation is used:
a = alpha decay
Source of data:
p- = beta decay ec = electron capture
Table of Radioactive Isotopes, E. Browne, R.B. Firestone (V.S. Shirley,editor), publ. by John Wiley & Sons, USA, 1986. The tables used are:
(a) A-chain tables, pp.208 ff.: for X-ray group energies and decayintensities (columns 4-6) .
(b) X-ray tables, pp.C-19 to C-24: for notation and all other data.
Note: The data were revised in October 1997. The new "Table of Isotopes", 8th
Edition, R.B. Firestone, V.S. Shirley (Ed.), J. Wiley & Sons, Inc, USA, 1996contains in vol.2, pp. F-42 to F-77 the same data as (b) above. However, the data(a) above are not contained therein. Therefore the old "Table of RadioactiveIsotopes" is also used here.
Table A-4
elementtype
8 1 - T l
K a lK a 2K 151K 153K 155K 151"K 152K 154K 0K 152'
A-5: Thermal neutron cross sections, resonance integralsand related parameters
This table contains thermal neutron cross sections, Westcott g-5actors andresonance integrals for capture and fission (if significant). All data are takenfrom [1] unless indicated by footnotes, as this source gives uncertainties whichare not included in the more recent data files ENDF/B-6 (only sometimes includedin the text information) or JENDL-3.
Description of table entries:
The second column describes the thermal neutron cross section of thefollowing type:
oo 2200 xa/s cross sectiono Maxwellian average cross section (kT = 0.0253 eV)or cross section in a thermal reactor neutron spectrumm cross section leading to a metastable state of productg cross section leading to ground state of productm+g sum cross sectiong: Westcott g-factor for the deviation of the cross section from the 1/v
shape for a Maxwellian neutron spectrum with kT = 0.0253 eV
Resonance Integral: Infinite dilution resonance integral including the 1/v part
ENDF/B-6: the US Evaluated Nuclear Data File, version 6
JENDL-3: the Japanese Evaluated Nuclear Data Library,version 3
The data were revised in October 1997. The revised data were taken from theOctober 1996 revision of the ENDF/B-6 Standards File (NNDC Brookhaven, USA) . Theevaluated data files of complete o(E) data, ENDF/B-5 and JENDL-3 are available fromthe 4 Data Centres (see Introduction) upon request.
Table A-5
Nuclide
90-Th-232
92-U-233
92-U-234
92-U-235
92-U-236
92-U-237
92-U-238
93-Np-237
Thermal
oo-capt
oo-captao-fiss
oo-capt
ao-captoo-fiss
o0-capt
o-capt
o°-capt
ao-capt
Neutron Cross(b)
7.37
45.5529.1
99.8
98.59584.81
5.11
443.
2.680
175.9
Sections
±
±±±
±+
+
0.06
0 . 71 .2
1 .3
0 . 81.11
0.21
±167.
±
±
0.019
2 . 9
Westcottg-factor
0.9982
1.00400.9955
0 .9903
0.98970.9786
1.0009
0.982
2)± 0 .0015
± 0 .0008± 0 .0008
ResonanceIntegral
85. ±
137. ±760. ±
660. ±
143.4 ±277.5 ±
360. ±
1200. ±
277. ±
640. ±
(b)
3 .
6 .1 7 .
7 0 .
6 . 05 . 0
1 5 .
200.
3 .
5 0 .
- 26 -
Nuclide
93-Np-239
94-PU-238
94-PU-238
94-PU-239
94-PU-240
94-PU-241
94-PU-242
95-Am-241
95-Am-242g
95-Am-242m
95-Am-243
96-Cm-242
9 6-Cm-2 4 3
96-Cm-244
Thermal Neutron Cross Sections(b)
or-capt
o0-capt
o0-f iss
oo-capto0-fiss
o0-capt
o0-captao-fiss
ao-capt
ao(g)-capto0(m) -captoo(m+g)-captoo-fiss
o-fisso0-capt
o-capto0-fiss
o0-capto-fiss
o-captoo-fiss
oo-captoo-fiss
oo-captoo-fiss
6 8 .
540.
17.9
271.43747.99
289.5
361.291012.68
18.5
533.54.
587.3.20
2100.5500.
2000.6950.
±
±
±±+
±
±±
±
±+±+
10. 7)
7 .
0 . 4
2 .141.87
1.4
4 .956.58
0 . 5
13 .5.
12. 5)0.09
±200.
±600.±280.
75.1 ±0.1983±
16.5.064
130.617.
15.21.04
±
+±
1.80.0043
5.6)
10.20 .
1.20.20
Westcottg-factor
0.9563
0.9562
1.1435 A)1.0563 ± 0.0022
1.0264
1.0381.046 ± 0.006
1.0096
t o be computed
1.0510.996
1.104
1.014
1.0051.0054
0.9990.989
ResonanceIntegral (b)
162.
3 3 .
200.301.
8100.
179.572.
1115.
1230.195.
1425.14.
1260.391.
246.1800.
1820.9.
110.20.
215.1570.
650.12.
96
4
0
5
±
±±±
±
±+
±±+
±
±
±
++
++
1 5 .
5 .
20 .10.
200.
3 j
3j
4 0 .
100.20 .
100.1.0
i)
I \
6j
65.
70.1.
2 0 .
20 .100.
30.2 . 5
6)
7)
JENDL-3 data are used. There is a discrepancy between ENDF/B-6 andJENDL-3; no value given by Mughabghab [1]
calculated from o(abs) and g(abs), 574.7 ± 1.0 b and 0.9996 ± 0.0011,respectively
oo cross sections for capture and fission taken from ENDF/B-6 standard, RIvalues taken from JENDL-3
calculated from a(abs) and g(abs), 1019.42 ± 2.9 b and 1.0768 ± 0.003,respectively
Mughabghab's [1] value not in agreement with ENDF/B-6 (620 ± 13 b)
value from JENDL-3; no values given in [1] and ENDF/B-6
JENDL-3 contains more recent capture data, but without uncertainty:oo=37.0 barn, RI=445 barn.
- 27 -
A-6: Average number of neutrons emitted per fission(v)
Average number of total and prompt neutrons:
The average numbers of total neutrons for thermal neutron induced fission ofU-233,235, Pu-239,241 and spontaneous fission of Cf-252 are taken from the mostrecent version of the internationally agreed standards file [1] . The promptneutron data for the same reactions were calculated from the total and delayedneutron data.
For the other nuclides the average numbers of total and prompt neutrons forthermal neutron induced and spontaneous fission, which are identical within theiruncertainties, are taken from [2], which is the only and most recent source thatcontains all these data. In the evaluation [2], all data were normalised to v ofU-235 thermal neutron induced fission and Cf-252 spontaneous fission. Thenormalisation values used in [2] are almost identical to the standard values from[1] . v data as a function of incident neutron energy are included in the large datafiles, (e.g. ENDF/B-6 or JENDL-3). Some formulae of the energy-dependence can befound in [6], e.g. for U-235, U-238 and Pu-239.
No evaluations of total or prompt v data from fission in a fast reactor orfission neutron spectrum are available.
Average number of delayed neutrons:
The total delayed neutron yield is listed in the last column. A recentOECD/NEA committee meeting recommended [5] the use of delayed neutron yieldsevaluated from direct measurements rather than those obtained from summationcalculations. (In the latter method, delayed neutron yields are derived fromindividual delayed neutron precursor data and fission yields, and there the chargedistribution, which is uncertain in many cases, has a significant effect on theresults.) Following this recommendation, the data of Tuttle [3], partially updated[5] by results of new measurements, are chosen for the tables. Recent results fromsummation calculations [4] are used for nuclides where no data are given in [3,5].
Source of data:
[1] ENDF/B-6 Standards file 1990 (available from Nuclear Data Centres uponrequest, when requested from NDS: documentation and data are in IAEA-NDS-88see the help-pages for further informations).
[2] N.E. Holden and M.S. Zucker, Int. Conf. on Nuclear Data for Basic and AppliedScience, Santa Fe, New Mexico, USA, 13-17 May 1985, proceedings p.1631.
[3] R.J. Tuttle, INDC(NDS)-107 (1979) 29
[4] R.W. Mills, Thesis, University of Birmingham (UK), March 1995: the mostrecent UKFY3 fission yields have been used.
(5] J. Blachot et al. , "Status of Delayed Neutron Data - 1990", reportNEACRP-L-323 (1990)
[6] J.Frehaut, "Coherent Evaluation of Vp for U-235, U-238 and Pu-239", ReportNEANDC(E)238 (INDC(Fr)67) , 1986.
ENDF/B-6: the US Evaluated Nuclear Data File, version 6
JENDL-3: the Japanese Evaluated Nuclear Data Library,version 3
The evaluated data files of complete v data, as part of ENDF/B-6 and JENDL-3,are available from the 4 Data Centres (see Introduction for further information)upon request.
- 28 -
Table A-6.1: Average numbers of total, prompt and delayed neutrons from thermalneutron fission of U-233,5, Pu-239,41, Am-241, Cm-243,5 andspontaneous fission of Cm-242,4, Cf-252
nuclide
U -233
U -235
Pu-239
Pu-241
Am-241
Cm-242
Cm-24 3
Cm-2 4 4
Cm-245
Cf-252
2.4946
2.4320
2.8815
2.9453
3.22
2.54
3.43
2.72
3.75
3.7676
total
± 0.0040
± 0.0036
± 0.0052
± 0.0059
±0.04
±0.02
± 0.14
±0.02
± 0.10
± 0.0049
[1]
[1]
[1]
[1]
[2]
[2]
[2]
[2]
[2]
[1]
2.4872
2.4153
2.8752
2.9301
3.22
2.54
3.43
2.72
3.75
3.7590
prompt
+
+
±
+
+
+
+
±
±
±
0.0040
0.0036
0.0052
0.0059
0.04
0.02
0.14
0.02
0.10
0.0049
[1]
[1]
[1]
[1]
[2]
[2]
[2]
[2]
[2]
[1]
0.00667
0.0166
0.00654
0.0152
0.00411
0.00125
0.00222
0.00330
0.00440
0.0086
delayed
± 0.00029
± 0.0005
± 0.00026
± 0.0011
± 0.00057
± 0.00033
± 0.00066
± 0.00098
± 0.00122
± 0.0010
[3]
[5]
[5]
[3]
[4]
[4]
[4]
[4]
[4]
[3]
Table A-6.2: Average numbers of delayed neutrons from fission in a fast reactorneutron spectrum
There are only 2 sets of evaluated prompt neutron multiplicity distributionsfor thermal neutron induced and spontaneous fission known to us. The data arereproduced below (no new data since preliminary issue) .
N.E. Holden and M.S. Zucker, Nucl.Sci.Eng. 98 (1988) 174
Table 7.2: P(v) values for spontaneous fission (without uncertainties)
0
1
2
3
4
5
6
7
8
9
Cm-242
0.02125
0.14674
0.32675
0.32683
0.13751
0.03738
0.00259
0.00076
0.00019
Cm-244
0.01501
0.11617
0.29984
0.33316
0.18378
0.04298
0.00879
0.00027
Cf-252
0.00217
0.02556
0.12541
0.27433
0.30517
0.18523
0.06607
0.01414
0.00186
0.00006
Source of data:
N.E. Holden and M.S. Zucker, Int. Conf. on Nuclear Data for Basic and AppliedScience, Santa Fe, New Mexico, USA, 13-17 May 1985; proceedings p. 1631.
- 30 -
A-8 : Delayed neutron six-group parameters
An OECD/NEA committee recommended [1] the group parameters from the summationcalculations of Brady and England [2] because of the overall consistency of thedata and because the overall differences with experimental results (like [3]) weresmall enough so that the data of [2] can be used without sacrificing accuracy.Following this recommendation and because there was no new evaluation since then,we have adopted the group parameters of [2] . No evaluated group parameters for Cm-242,243,244 are presently available.
Description of table entries:
Aayield
References:
delayed neutron group decay constantratio (del.neutron group yield)/(total del.neutr. yield)delayed neutron group yield (in % per fission)
[1] J. Blachot et al. , "Status of Delayed Neutron Data - 1990", report NEACRP-L-323 (1990)
[2] C M . Brady and T.R. England, Nucl. Sci. Eng. 103 (1989) 135[3] G.R. Keepin, "Physics of Nuclear Kinetics", Addison-Wesley Publishing Co.,
Reading, Mass. (1965), tables on pages 86, 87 and 90
Table A-8: Delayed neutron six-group parameters from [2]
group
123456
123456
123456
123456
A (sec"1)
0.01310.03500.12720.32870.91002.8206
0.01330.03250.12190.31690.98862.9544
0.01330.03120.11620.28880.85612.7138
0.01330.03050.11520.29740.84772.8796
J__i_90-Th-232
0.03640.12590.15010.44060.16630.0808
J_ yield (%)
fast
0.19330.6690.7972.3400.8830.429
90-U-235 thermal
0.03800.19180.16380.34310.17440.0890
94-PU-238
0.03770.23900.15770.35620.15900.0504
94-PU-240
0.03200.25290.15080.33010.17950.0547
0.06310.3180.2720.5700.2900.148
fast
0.01770.1120.0740.1670.0750.0237
fast
0.03040.2400.1430.3140.1710.0520
A (sec"1
0.01290.03330.11630.29330.79432.3751
0.01360.03130.12330.32370.90603.0487
0.01330.03010.11350.29530.85372.6224
0.01370.02990.11360.30780.85693.0800
,| .
92-U-233
0.06740.19270.13830.27980.11280.2091
92-U-238
0.01390.11280.13100.38510.25400.1031
94-PU-239
0.03060.26230.18280.32830.14820.0479
94-PU-241
0.01670.24040.14740.34300.18980.0627
[ yield (%)
thermal
0.04500.12850.09220.18660.07520.1395
fast
0.06100.4950.5751.6911.1150.453
thermal
0.020010.17150.11960.21470.09690.0313
thermal
0.02540.3650.2240.5210.2880.095
- 31 -
group
123456
123456
A (sec'1) [ a
94-PU-242 3
0.01360.03020.11540.30420.82723.1372
0.01960.23140.12560.32620.22550.0716
yield (%)
fast
0.04330.5110.2780.7210.4980.158
96-Cm-245 thermal
0.01340.03070.11300.30010.83402.7686
0.02220.17880.16720.37060.20540.0559
0.009880.07960.07440.16490.09140.0249
• 1
A (sec"1) yield (%)
95-Am-241 thermal
0.01330.03000.11450.29490.88182.6879
0.03050.27600.15310.31220.18250.0457
0.01180.10680.05920.12080.07060.0177
98-Cf-252 spontaneous
0.01360.02910.10680.30240.81732.6159
0.01240.30520.18130.29920.17290.0290
0.01070.2620.1560.2570.1490.0249
- 32 -
SECTION B: FISSION PRODUCT NUCLEAR DATA
The table below lists the fission products for which half-lives (T^), Y~raYdata and capture cross sections (0) as well as branching fractions to isomericstates in decay (br) and neutron capture (not indicated below) are given in thisSection.
nuclide 7*4 br Y~raYs °
Kr M +
Br-85 +
Kr-85m +
Kr-85 + + +
Zr M +
Zr-95 + + + +
Nb-95m + + +
Nb-95 + +
Mo 1) +
Ru ') +
Ru-103 + + +
Ru-106 + +
Rh-106 + +
Sb-125 + +
Xe >) +
1-131 + + +
Xe-131m + + +
1-133 +
Xe-133m + +
Xe-133 + + +
Cs-133 +
Cs-134 + + + +
1-135 + +
Xe-135m + +
nuclide 1*4 br Y~rays o
Cs-135 +
Cs-137 + + +
Ba-140 + +
La-140 + +
Ce-141 + +
Pr-141 +
Pr-143 +
Ce-144 + + +
Pr-144 + +
Nd ') +
Nd-147 + + +
Pm-147 + + +
Pm-14 8m + + + +
Pm-148 + + +
Pm-149 + +
Pm-151 + +
Sra x) +
Sm-151 + +
Sm-153 + +
Eu-151 +
Eu-152 +
Eu-153 +
Eu-154 + + + +
Eu-155 + + +
') Stable isotopes for mass spectrometric measurements
Nuclides with A=147-153 are included for calculating the formation of Eu-154.
- 33 -
B-l: Half-lives and decay branching fractions
Table B-l.1: Half-lives and decay mode branching
Description of table entries:
decay mode: (3- beta decayIT isomeric transitionec electron capture
units: s secondm minuteh hour
d dayy year=365.2422 days
rel err: relative error (in %)
branching: given for each decay mode (should sum up to 100%)
Source of data:
ENSDF file. Selected nuclides taken from IAEA-TECDOC-619, September, 1991.
nudide
36-Kr- 85
40-Zr- 95
41-Nb- 95m
41-Nb- 9 5
44-RU-103
44-RU-106
45-Rh-106
51-Sb-125
53-1 -131
54-Xe-131m
54-Xe-133m
54-Xe-133
55-CS-134
53-1 -135
54-Xe-135m
54-Xe-135
55-CS-137
56-Ba-140
57-La-140
units
y
d
d
d
d
y
s
y
d
d
d
d
y
h
m
h
y
d
d
half-lifevalue
10.756
64.02
3.608
34.975
39.26
1.0228
29.80
2.7589
±
±
±
±
±
±
±
±
8.02070±
11.84
2.19
5.243
2.0648
6.57
15.29
9.14
30.18
12.752
1.6781
±
±
+
+
+
+
+
±
+
±
0.018
0.04
0.033
0.007
0.02
0.0004
0.08
0.0016
0.00011
0.07
0.03
0.001
0.0010
0.02
0.05
0.02
0.15
0.003
0.0003
rel err
( 0.17)
( 0.06)
( 0.92)
( 0.02)
( 0.05)
( 0.04)
( 0.27)
( 0.06)
( 0.001)
( 0.6 )
( 1.4 )
( 0.02)
( 0.05)
( 0.3 )
( 0.33)
( 0.24)
( 0.5 )
( 0.02)
( 0.01)
decaymode
13-
13-
IT13-
B-
13-
13-
(3-
13-
13-
IT
IT
13-
13-ec
B-
IT13-
13-
13-
13-
13-
braching(percent/decay)
100.000
100.000
94.4 :5.6 :
100.000
100.000
100.000
100.000
100.000
100.000
100.000
100.000
100.000
99.9997 :0.0003 :
100.000
99.9960.004
100.000
100.000
100.000
100.000
t 0.6t 0.6
b 0.0001b 0.0001
- 34 -
nuclide
58-Ce-141
58-Ce-144
59-Pr-144
60-Nd-147
61-Pm-147
61-Pm-148m
61-Pm-148
61-Pm-149
61-Pm-151
62-Sm-151
62-Sm-153
63-EU-154
63-EU-155
units
d
d
m
d
y
d
d
d
d
y
d
y
y
half-lifevalue
32.501
284.893
17.28
10.980
2.6234
41.29
5.370
2.2110
1.1830
90.0
1.9280
8.593
4.7611
±
±
±
±
±
±
±
±
±
±
±
±
0.005
0.008
0.05
0.010
0.0002
0.11
0.009
0.0020
0.0016
6.0
0.0041
0.004
0.0013
rel err
( 0.03)
( 0.003)
( 0.29)
( 0.09)
( 0.01)
( 0.27)
{ 0.17)
( 0.09)
( 0.14)
( 6.7 )
( 0.21)
( 0.09)
( 0.03)
decaymode
B-
B-
B-
B-
B-
fl-IT
B-
(1-
B-
B-
B-
B-ec
fl-
braching(percent/decay)
100.000
100.000
100.000
100.000
100.000
95.05.0
100.000
100.000
100.000
100.000
100.000
99.9800.020
100.000
1+ 1
+
+1 +1
0.40.4
0.0100.010
Table B-l.2: Branching to daughters
Branching fractions are given for some important daughter products.
Source of data: ENSDF file
nuclide
35-Br- 85
36-Kr- 85m
40-Zr- 95
53-1 -131
53-1 -133
53-1 -135
daughter
36-Kr- 85
36-Kr- 85
41-Nb- 95m
54-Xe-131m
54-Xe-133m
54-Xe-135m
branching(percent/decay)
0.18 ± 0.0
21.4 ± 0.4
1.13 ± 0.007 l)
1.10 !)
2.88 ± 0.03 !)
15.7 ± 0.3 *)
Branching to ground state = 100-branching to metastable state
- 35 -
B-2: Gamma ray energies and emission probabilities
Description of table entries:
1" column: fission product nuclide2nd column: y~ray energies and their uncertainties in keV3rd column: v-ray emission probabilities and their lo uncertainties in percent per
decay and relative uncertainties (in %) in brackets.4th column: systematic (relative) error contributions (in %) from conversion of
relative to absolute intensities for each nuclide (included in theerrors given in the 3rd column.)
Source of data:
E. Browne, R.B. Firestone: Table of Radioactive Isotopes (V.S. Shirley, ed.), JohnWiley & Sons, NY, 1986. Updates to this handbook from the Berkeley decay data file(data derived from ENSDF), E. Browne, private communication, 1986/87.
Note: The data were revised in October 1997. Updated values of energies andemission probabilities were taken from the ENSDF data file as retrieved by MEDLISTprogram, the version dated May 1997.
B-3: Thermal neutron capture cross sections and resonanceintegrals
The main reference used for fission product cross section data are theevaluations by Gryntakis [1] and Mughabghab [2,3]. The more recent data filesENDF/B-6 [7] or JENDL-3 [6] were rarely used because they do not contain datauncertainties (except in the text information for some nuclides in ENDF/B-6). Thecompilation by De Corte [4] was not used (except in one case) because recommendeddata are not given for all fission products.
The thermal cross sections in [1] agree with those in [2] or [3] in almostall cases, and the values are taken from [1] (more recent) unless indicated byfootnotes.
The agreement for resonance integrals is not so good. In cases ofdifferences the data were selected by comparison to ENDF/B-6 and JENDL-3 and/or byone of the following criteria (special cases are indicated by footnotes):
The values of [1] were chosen when:
no resonance integral is given in [2] or [3], ormore recent measurements were included in [1], orthe resonance integral given in [2] or [3] was calculated fromresonance parameters, but did not include more recent measurements.
The values of [2] or [3] were chosen when:
more recent measurements were included, orthe value in [1] was deduced from old measurements only, and the valuein [2] or [3] was calculated from resonance parameters (indicated by "C")which often included more recent measurements.
NOTE: The data were revised in October 1997. Comparison was made with the mostrecent libraries JEF-2.2 and JENDL-3.2. The changes were made only in cases whennew measurements justified them.
Description of table entries:
The second column describes the thermal neutron cross section of thefollowing type:
oc 2200 m/s cross sectiona Maxwellian average cross section (kT = 0.0253 eV)or cross section in a thermal reactor neutron spectrumm cross section leading to a metastable state of productg cross section leading to ground state of productm+g sum cross section
Resonance Integral: Infinite dilution resonance integral including the 1/vpart, "Ref." gives the source of the tabulated resonance integral, "C" stands forcalculation from resonance parameters.
Source of data:
[1] G. Gryntakis et al., Thermal Neutron Cross Sections and Infinite DilutionResonance Integrals, in "Handbook on Nuclear Activation Data", IAEA TechnicalReport Series No. 273 (1987), page 199
Original value in [1] = 1045 ± 265 b, adjusted here (within the error limits)to give the correct sum (m+g).Te higher value of [1] is supported by the data from JENDL-3 (2199 b) andENDF/B-6 (2197 b) , whereas [3] gives 2064 ± 100 b.[3] used, as uncertainty is given. Other values: 334.5 b [1], 420.2 b(JENDL-3), 330 b (ENDF/B-6).Taken from [4] because of discrepancies between [1] and [3].[1] gives 603 and 3414 b respectively, but recent evaluations ([4], ENDF/B-6)support the lower values.Both sets of data given for comparison. Other values: ENDF/B-6: same as [3],JENDL-3: 4071 b and 6755 b respectively.
- 42 -
SECTION C: FISSION PRODUCT YIELDS
The tables contain yield sets from the US and UK evaluated fission yieldfiles, which result from the presently largest evaluation efforts. This is inaccordance with the recommendations of an IAEA Coordinated Research Programme onthe Compilation and Evaluation of Fission Yield Nuclear Data that not a single setof fission yields should be recommended. A third file of fission yield data fromChina is presently being revised; it is expected that it can be included in thefuture.
C-l: Chain yields and selected cumulative yields
Fission yields are given for thermal neutron fission of U-233,235, Pu-239,241and for fast neutron fission of Th-232 and U-238. The Tables contain cumulativeand chain yields 2 0.01-0.001 %. In addition, the most important ternary fissionyields are presented. Cumulative yields are given seperatly only if they differsignificantly from the respective chain yields, or for some important fissionproducts to show the (even small) difference.
Description of table entries:
FP: Chain yields are indicated by "A=". Otherwise the nuclide is listed forwhich the cumulative yield is given.
The fission yield values are given in percent per fission and tabulated in2 different representations as extracted from the files:
US file: fixed point numbers and relative errors (in %)UK file: floating point numbers and absolute errors
Source of data:
US file: ENDF/B-6 Fission Yield FileUK file: R.W. Mills, "UKFY3",the latest update of the UK library of independent andcumulative fission product yields, in ENDF-6 format (1996). The file UKFY3contains also several other tables of fission yield data and discrepances.
Both the US file and the UK file are available on magnetic tape from the DataCenters.
Table C-l.l: Th-232 fast fission
H -
He-
He-
A=
A=A=
A=
A=
A=
A=
A=
FP
3
3
4
77
78
79
80
81
82
83
84
Kr-85
US file
0.011765
0.03528
0.076873
0.194213
0.469835
1.075426
2.169280
4.026097
0.8334
error
8.
11.11.
16.
11.
16.
2.0
1.4
1.4
UK file
7.0030-
7.0081-
1.0164-
1.0903-
3.2701-8.8309-
2.1836-
5.0116-
1.0746+
1.9980+
4.4033+
9.9431-
3
3
1
2
22
1
1
0
0
0
1
error
2.2139-
2.2139-
3.1047-
2.6793-
1.0566-
2.6661-
6.5647-
1.5023-
3.0393-
4.2049-
7.2294-
2.3040-
3
3
2
3
2
2
2
1
1
11
1
- 43 -
FP
A= 85
A= 8 6A= 87A= 8 8
A= 8 9
A= 90
A= 91
A= 92
A= 93
A= 94
A= 95
A= 96
A= 97
A= 98
A= 99
A=100
A=101
A=102
A=103
A=104
A=105
A=106
A=107
A=108
A=109A=110
A=lll
A=112
A=113
A=114
A=115
A=116
A=117
A=118A=119
A=120
A=121
A=122
A=123
A=124
A=12 5
A=126
A=127
A=128
A=129A=130
Xe-131m
A=131
A=132
Xe-133m
US file
4.167428
6.5876017.0735937.260427
7.467815
7.924058
7.363992
6.920399
6.697280
5.562996
5.652666
4.776764
4.425500
3.680042
2.944060
1.370638
0.713542
0.367805
0.155461
0.090313
0.051481
0.048561
0.051075
0.061347
0.066215
0.070997
0.071619
0.078263
0.078066
0.073423
0.077003
0.073801
0.0738220.0632810.057210
0.054327
0.048821
0.036527
0.029354
0.026475
0.032954
0.048129
0.101355
0.182599
0.252076
0.945582
0.022692
1.620949
2.9688560.1165
error
1.4
2.0
2.8
2.0
2.8
4.0
2.0
2.8
4.0
4.0
2.0
16.
2.0
6.
2.0
6.
11.
11.
4.0
11.
2.8
8.
11.
16.
4.0
16.
6.
6.
4.0
16.
2.8
16.
2.8
11.
16.
16.
6.
16.
16.
16.
11.
16.
4.0
16.
4.0
11.
4.0
2.0
1.4
4.0
UK file
4.6596+
6.9370+
6.7234+6.9651+7.3129+
8.0327+
7.0022+
7.1301+
6.1532+
5.5177+
5.6274+
5.0207+
4.3891+
3.5875+
2.8882+
1.6104+
8.1881-
3.6240-
1.5417-
8.7640-
7.0452-
5.4287-
5.3308-
5.3368-
5.3076-5.8727-
6.4551-
6.8870-6.8001-
6.7013-
6.5799-
6.7917-
6.8008-6.7678-
6.6878-
6.5682-
6.4106-
6.2161-
5.9945-
5.7677-
5.6283-
5.9543-
8.0179-
1.7189-
4.5684-
9.0836-
1.6682-
1.5445+
2.6562+1.3399-
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
1
1
1
2
2
2
2
2
2
2
2
2
2
2
2
2
22
2
2
2
2
2
2
2
2
2
1
1
1
2
0
0
1
error
8.7907-
1.1514+1.2404+1.2050+
1.0932+
1.2038+
8.5668-
1.3574+
1.1564+
8.8801-
8.9501-
1.3514+
8.6974-9.7598-
4.5217-
5.1890-
2.7335-
9.2444-
9.1892-
2.1156-
2.6677-
6.8126-
1.4256-
1.7554-
1.6976-
1.7396-
1.5117-
1.6900-
2.2248-
2 2151-
1.7689-
2.1911-
2.1907-
2.1940-
1.8948-1.5725-
2.0746-
1.9943-
1.9410-
1.8689-
1.8254-1.9303-
1.4860-
5.5112-1.9401-2.7901-
2.7551-
2.5507-
4.2986-
2.1319-
1
0
0
0
0
0
1
0
0
1
1
0
1
1
1
1
1
2
3
2
3
3
2
2
3
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
1
1
3
1
1
2
- 44 -
FP
A=133
A=134
Xe-135m
Xe-135
A=135
A=136
A=137
A=138
A=139
A=140
A=141
A=142
A=143
A=144
A=145
A=146
A=147
A=148
A=149
A=150
A=151
A=152A=153
A=154
A=155
A=156
A=157
US file
4.046220
5.351795
0.8187
5.5280
5.5287845.621469
5.839457
6.449821
7.096623
7.877878
7.463862
6.540381
6.6472057.916097
5.338663
4.554332
2.978662
2.005246
1.083641
0.561977
0.363657
0.0755450.031009
0.006876
0.003617
0.002690
0.000932
error(%)
2.0
2.0
4.0
2.0
2.0
2.0
4.0
6.
2.0
2.0
2.8
2.8
2.0
2.8
2.0
2.8
2.8
2.8
4.0
23.
6.
16.
11.
23.
23.
8.
23.
UK file
4.6516+5.8608+
8.9306-
5.7023+
5.7026+5.6481+
6.5851+
6.3826+
7.3978+
7.7204+
7.0915+
6.3190+
6.2965+7.2697+
5.1219+
3.6439+
2.8614+
1.8882+
1.1366+
8.9271-
4.0995-3.1624-
2.0441-
6.3121-
1.5829-
2.5201-
8.6279-
0
0
1
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
1
1
1
1
2
2
3
4
error
7.2172-8.8907-
1.5385-
9.9094-
8.8759-
8.1524-
1.2133+
1.0056+
1.1414+
1.2160+
9.7706-
1.3528+
1.0190+
1.1770+
8.8866-
9.8019-
1.6487-
3.5169-
2.7409-
3.3157-
8.8839-1.0866-
4.8310-
2.0881-
5.1861-
7.0574-
3.6392-
1
1
1
1
1
1
0
0
0
0
2
0
0
0
1
1
1
1
1
1
2
1
2
2
3
4
4
Table C-1.2: U-233 thermal fission
H -
He-
A=
A=
A=
A=
A=
A=
A=
A=
A=
A=
FP
- 2
- 3
75
76
77
78
79
80
81
82
83
84
Kr-85
A=
A=
A=
85
86
87
US file
0.007981
0.013847
0.025959
0.053838
0.143515
0.234071
0.367786
0.586339
1.014543
1.689426
0.52340
2.237148
2.844415
4.018205
error(%)
23.
23.
16.
16.
16.
16.
4.
2.8
1.0
1.0
0.35
1.0
1.4
1.4
UK file
8.4660-
9.6910-
0.6584-
1.7072-4.1328-
6.6576-
1.3472-
2.6259-
3.8190-
5.9895-
1.0827+
1.6937+
5.2674-
2.1956+
3.0777+
4.0428+
4
3
3
2
2
2
1
1
1
1
0
0
1
0
0
0
error
2.2832-
2.3320-
0.1001-
2.4978-
5.2760-
8.6450-
1.7242-
3.3735-
5.0796-
8.0280-
1.4597-
2.2116-
7.2449-
2.9347-
4.0054-
4.8337-
4
3
3
3
3
3
2
2
2
2
1
1
2
1
1
1
- 45 -
FP
A= 88
A= 8 9
A= 90A= 91
A= 92
A= 93
A= 94
Zr-95
Nb-95m
A= 95
A= 96
A= 97
A= 98
A= 99
A=100
A=101
A=102
A=103
A=104A=105
A=106
A=107
A=108
A=109
A=110
A=lll
A=112
A=113
A=114
A=115A=116
A=117
A=118
A=119
A=120
A=121
A=122
A=123
A=124
A=125
A=126
A=127
A=128
A=129
A=130
Xe-131m
A=131
Te-132
A=132
Xe-133m
US file
5
6
6
6
6.
6.
6
6.
0.
6.
5.
5.
5.
4.
4.
3.
2.
1.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
1.
2.
0.
3.
4.
4.
0.
465197
340165
789072485957
552445
978996
831345
3490
063524
349605
678962
515746
189312
910973
459039
171242
402804
573207980193
495809
246245
114532
075767
039405
038664
021600
013304
013562
012860
014982
013202
014124
015417
018558
021829
023082
040969
060415
074624
116962
226118
555457
836918
591337
091632
050486
604300
7590
953559
2111
error
1.
1.
1.
1.
1.
1.
1.
2.
2.
1.
1.
1.
1.
1.
1.
1.
1.
2.
2.
2.
2.
4.
4.
16.
4.
8.
8.
11.
11.
6.
16.
11.
11.
16.
8.
8.
8.
23.
16.
8.
8.
11.
8.
16.
11.
2.
0.
2.
0.
23.
4
4
4
0
0
0
4
0
0
0
0
4
4
4
0
8
8
7
8
7
5
6
6
6
6
6
6
6
6
6
5
5
5
5
4
3
2
1
9
4
2
1
7
4
3
2
1
1
1
1
1
1
1
1
1
1
1
2
3
1
2
49
1
2
3
3
4
4
2
UK file
.5670+
.2179+
.7451+
.5631+
.4868+
.7946+
.7049+
.2669+
.9731-
.2678+
.6549+
.5004+
.1883+
.0432+
.4144+
.2493+
.4643+
.4597+
.5898-
.9628-
.4968-
.1498-
.8859-
.1746-
.9207-
.4458-
.4221-
.5813-
.7384-
.8971-
.7651-
.5213-
.5681-
.5955-
.7653-
.8586-
.9598-
.2279-
.2291-
.1634-
.3308-
.6784-
.2148-
.5983+
.5002+
.8458-
.5522+
.6234+
.8366+
.0210-
0
0
0
0
0
0
0
0
2
0
0
0
0
0
0
0
0
0
1
1
1
1
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
2
1
1
1
1
0
0
2
0
0
0
1
6.
7.
8.
7.
7.
8.
8.
8.
9.
8.
7.
6.
6.
6.
5.
4.
3.
1.
1.
6.
3.
1.
1.
6.
5.
3.
2.
2.
2.
2.
2.
2.
2.
2.
2.
2.
2.
3.
4.
1.
3.
1.
1.
2.
3.
5.
4.
6.
6.
2.
error
8688-
9010-
7165-7747-
9808-
7873-
8898-
1974-
1198-
4540-
6178-
7437-
6600-
5972-
8134-
3151-
2791-
9100-3127-
5199-2990-
6312-
1238-
0542-
5531-
5046-
0306-
4853-
7912-
6071-7065-
1179-
1887-
1935-
3884-
6069-
7501-
4803-
4093-
6378-
6234-
0573-
3405-
3691-
7061-
1343-
7420-
0620-
2961-
7491-
1
1
1
1
1
1
1
1
3
1
1
1
1
1
1
1
1
1
2
2
2
2
2
3
3
3
3
3
3
3
3
3
3
3
3
3
3
3
3
2
2
1
1
1
1
3
1
1
1
2
- 46 -
FP
Xe-133
A=133
A=134
I -135
Xe-135mXe-135A=135
A=136
Cs-137
A=137
A=138
A=139
Ba-140
La-140
A=140
A=141A=142
A=143
Ce-144
A=144
A=145
A=146
A=147
A=148
A=149
A=150
A=151
A=152
A=153
A=154
A=155
A=156
A=157
A=158
A=159
US file
5.950
5.950570
6.306880
5.0320
1.54606.25906.265223
6.905353
6.7540
6.757385
5.907377
6.305604
6.3980
6.4250
6.424816
6.480480
6.670707
5.965845
4.7260
4.726134
3.4440622.585897
1.738401
1.301585
0.778134
0.505712
0.315725
0.213639
0.103685
0.046690
0.021430
0.012794
0.006302
0.002055
0.000886
error
2.
1.
0.7
2.8
32.
2.
1.4
1.0
0.7
0.7
2.
2.8
2.8
2.
1.4
2.8
1.4
0.7
2.
0.7
1.
0.7
2.8
1.
2.8
1.4
2.
2.8
6.
2.8
16.
6.
8.
23.
6.
UK file
6.0874+
6.0875+
6.4101+
4.3758+
1.5009+5.5384+5.5546+
7.4858+
6.5728+
6.5817+
6.1540+
5.8658+
6.6076+
6.6259+
6.6259+
6.4182+
6.8314+5.9521+
4.6524+
4.6535+
3.4002+2.5361+
1.8101+
1.2918+
7.6062-
4.7745-
3.1932-
1.8370-
1.1144-
4.2773-
2.1866-
1.0885-
6.8821-
2.6497-
9.5497-
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
1
1
1
1
1
2
2
2
3
3
4
error
7.6723-
7.6965-
8.0917-
6.4814-
2.6336-7.1027-7.1527-
8.8505-
7.6218-
8.0489-
7.7550-
7.5325-
7.6218-
8.3741-
8.4053-7.7017-
8.4422-7.6507-
6.0243-
6.1579-
4.5515-3.3931-
2.4065-
1.7585-
1.0506-
6.6778-
4.5602-
2.7026-
1.9513-
6.4437-
3.6923-
1.5961-
9.9967-
4.2155-
1.3575-
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
2
2
2
2
3
3
3
4
4
4
Table 1.3: U-235 thermal fission
]
H -
H -
H -
He-
He-
A=
A=
A=
FP
1
2
3
3
4
77
78
79
US file
0
0
0
007961
020966
044732
error
8.
8.
6.
UK file
1.7110-
8.4000-
9.3140-
9.3140-
1.6990-
8.3895-
2.0322-
4.7151-
3
4
3
3
1
3
2
2
error
2.9483-
2.4389-
5.3176-
5.3176-
9.5049-
6.0364-
9.1351-
3.6568-
4
4
4
4
3
4
4
3
- 47 -
FP
A= 80
A= 81
A= 82A= 83A= 84
Kr-85
A= 85
A= 8 6
A= 87
A= 88
A= 8 9
A= 90
A= 91A= 92
A= 93
A= 94
A= 95
A= 96
A= 97
A= 98
A= 9 9
A= 100
A=101
A=102A=103
A=104
A=105
A=106
A=107
A=108
A=109
A=110
A=lll
A=112
A=113
A=114A=115
A=116
A=117
A=118
A=119
A=120
A=121
A=122A=123
A=124A=125
A=12 6
A=127
A=128
US file
0.128832
0.203680
0.3245690.5364351.002093
0.2834
1.318713
1.965113
2.560298
3.575006
4.733074
5.782353
5.8282456.021674
6.346743
6.472653
6.503326
6.340230
5.997223
5.790300
6.109164
6.292781
5.1729194.298778
3.031149
1.880825
0.964228
0.401576
0.1462020.054129
0.031223
0.025445
0.017432
0.013043
0.014205
0.0118330.012584
0.013249
0.012762
0.011346
0.012874
0.012609
0.013047
0.015485
0.0156580.026788
0.034022
0.058518
0.156991
0.348840
error
4.
2.8
2.80.50.7
0.35
0.35
0.5
0.5
0.7
1.0
1.0
0.70.7
0.7
0.7
0.7
1.0
0.7
0.7
1.0
0.7
1.0
1.0
1.0
1.0
1.4
1.0
2.8
4.
6.
4.
2.8
4.
4.
4.2.8
4.
4.
8.
8.
8.
6.
8.
2.88.
2.0
8.
2.8
2.8
UK file
1.2657-
1.9757-
3.2904-5.5742-1.0025+
2.8728-
1.3287+
1.9686+
2.5438+
3.5088+
4.7820+
5.8089+
5.8951+6.0110+
6.3404+
6.5010+
6.5570+
6.3005+
5.9378+
5.7651+
6.1594+
6.2316+
5.1492+
4.2701+
3.0802+
1.8685+
9.4711-
4.0922-
1.3909-5.7157-
2.8444-
2.5447-
1.9700-
1.1860-
1.5999-
1.2909-1.1389-
1.6099-
1.2223-
1.3249-
1.4904-
1.4425-
1.2590-
1.7992-
1.5051-3.1551-
2.6032-
5.9471-
1.2033-
3.3093-
1
1
11
0
1
0
0
0
0
0
0
00
0
0
0
0
0
0
0
0
0
0
0
0
1
1
1
2
2
2
2
2
2
22
2
2
2
2
2
2
22
2
2
2
1
1
error
5.6480-
9.0481-
1.3406-
2.2571-
4.7142-1.5098-
6.1233-
7.6887-
1.8613-
1.6668-
1.9254-
2.2460-
5.0951-4.7126-
2.7652-
2.5392-
2.5435-
2.4538-
4.5412-
2.7767-
2.3650-
2.3674-
1.9908-
1.6691-1.6023-
7.5748-
3.8642-
1.7994-
6.3035-2.8578-
3.1539-
1.9026-
8.0835-
6.8785-
7.8756-
6.3254-6.3085-
8.0499-
1.1609-
2.0526-
1.4184-
1.4517-
5.1622-
1.1689-6.1705-
2.6721-
1.3535-
5.5843-
4.9314-
1.3531-
3
3
22
2
2
2
2
1
1
1
1
111
1
1
1
1
1
1
1
11
1
2
2
2
3
3
3
3
4
4
4
44
4
3
3
3
3
4
3
43
3
3
3
2
- 48 -
FP
A=129
A=130
Xe-131m
A=131
A=132
Xe-133m
Xe-133
A=133
A=134
1-135
Xe-135mXe-135A=135
A=136
A=137
A=138
A=13 9
A=140
A=141
A=142A=143
A=144
A=145
A=146
A=147
A=148
A=149
A=150
A=151
A=152
A=153
A=154A=155
A=156
A=157
A=158
A=15 9
US file
0.5433861.810633
0.040470
2.890898
4.313407
0.1947
6.6990
6.699915
7.872644
6.2820
1.1020
6.5380
6.539455
6.318709
6.188944
6.768035
6.413852
6.220169
5.847414
5.849283
5.956198
5.499964
3.933647
2.997113
2.246885
1.673660
1.081705
0.653325
0.418797
0.266932
0.158290
0.0744390.032138
0.014854
0.006151
0.003286
0.001009
error
1.
2.
1.4
0.5
0.35
2.
0.5
0.35
0.5
1.4
1.4
0.7
0.35
0.35
0.5
0.5
0.7
0.5
1.0
0.5
0.35
0.35
0.35
0.35
0.7
0.35
1.0
0.5
1.0
1.0
2.8
1.0
4.2.8
8.
11.
6.
UK file
7.0797-
1.7900+
3.1249-
2.8931+
4.3173+
1.9070-
6.5863+
6.5863+
7.7897+
6.3616+
1.1514+6.5948+
6.5957+
6.3071+
6.2462+
6.7518+
6.4024+
6.3758+
5.8208+
5.8209+5.9659+
5.4759+
3.9510+
2.9834+
2.2211+
1.6802+
1.0488+
6.5019-
4.1789-
2.5240-
1.5106-
7.2739-3.1017-
1.3400-
6.6337-
1.9710-
1.0620-
1
0
2
0
0
1
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
1
1
1
12
2
2
3
3
3
error
3.1635-1.0182-
1.2451-
1.1527-
1.6928-
7.1606-
2.4777-
2.4827-
2.8834-
2.6479-
6.1262-2.5532-
2.5370-
2.3901-
2.7549-
2.6046-
2.4944-
2.4785-
4.3696-
2.6528-
2.2744-
2.0968-
1.5557-
1.1884-
1.9120-
6.7209-
4.2532-
2.6507-
1.7048-
1.0322-
6.1998-2.9817-1.2717-
5.4945-
4.3925-
2.4649-
7.0118-
2
1
3
1
1
3
1
1
1
1
2
1
1
1
1
1
1
1
1
1
1
1
1
1
1
2
2
2
2
2
3
3
3
4
4
4
5
Table C-1.4: U-238 fast fission
1
H -
He-
He-
A =
A=
A=
FP
3
3
4
78
79
80
US file
0
0
0
011222
032673
042741
error
23.
23.
16.
UK file
1.0262-
1.0262-
1.4880-
7.6701-
1.7866-
3.9122-
2
2
1
3
2
2
error
3.2419-
3.2419-
4.5467-
1.9624-
4.2626-
9.4491-
3
3
2
3
3
3
- 49 -
FP
A= 81
A= 82
A= 83
A= 84Kr- 8 5
A= 85
A= 8 6
A= 87
A= 88
A= 89
A= 90
A= 91
A= 92
A= 93
A= 94
Nb- 95m
A= 95
A= 96
A= 97A= 9 8
A= 99
A=100
A=101
A=102
A=103
A=104
A=105
A=106A=107
A=108
A=109
A=110
A=lll
A=112
A=113
A=114
A=115
A=116
A=117
A=118A=119
A=120
A=121
A=122A=123
A=124
A=125
A=12 6
A=127
A=128
US file
0.086206
0.213784
0.396237
0.825770
0.1486
0.743050
1.296448
1.625506
2.028030
2.761051
3.246924
4.039440
4.312441
4.913253
4.610062
0.051405
5.140443
6.017329
5.562461
5.944993
6.168192
6.697326
6.209007
6.447346
6.275279
5.035980
4.051243
2.4897221.445866
0.601420
0.252140
0.140760
0.071214
0.055901
0.046111
0.039257
0.037548
0.039314
0.037732
0.043176
0.039720
0.038713
0.036927
0.041073
0.044534
0.046461
0.048524
0.054089
0.136294
0.286086
error
23.
16.1.
1.
2.
1.
1.1.
1.
1.
1.
2.
2.
2.
2.
1.
1.4.0.1.1.
1.
1.
1.
1.
1.
1.
1.
8.16.
6.
16.
2.
4.
11.
16.
2.
11.
11.
11.11.
11.
8.
11.16.
11.
6.
6.
4.• 6.
4
4
0
00
4
4
4
8
8
0
0
70
4
0
4
0
4
0
4
4
UK file
8.1197-
1.6063-
3.0375-
5.5427-
193632-
9.0761-
1.1885+1.6507+
2.1889+
2.9511+
3.3527+
4.3157+
4.4009+
5.2053+
5.1650+
5.8435-
5.2644+
6.0618+
5.6850+
5.7868+6.2038+
6.5601+
6.3796+
5.9350+
5.9570+
4.6340+
3.7088+
2.4774+1.7371+
5.7704-
1.2762-1.0027-
6.7991-
4.0834-
3.0942-
3.4042-
3.7872-
3.1076-
2.7350-
2.4599-
2.3282-
2.1395-
2.0230-
1.9304-1.9533-
2.0638-
2.1184-
9.6592-
1.4606-
2.9689-
2
11
1
11
0
0
0
0
0
0
0
0
0
2
0
0
0
00
0
0
0
0
0
0
0
01
11
2
2
2
2
2
2
2
2
2
2
2
22
2
2
2
1
1
error
2.0204-
3.9659-
7.2435-
1.2667-
4.5351-
1.8276-
1.1339-
2.5987-
3.0018-
2.9383-
3.3442-
4.1110-
6.5592-
6.9016-
5.2331-
9.4816-
4.8831-
7.2568-
8.5074-8.9004-
7.1091-
6.2165-
6.1062-4.0079-
9.5226-
9.9407-
6.0340-
2.4567-
2.1617-1.4617-
1.9582-
2.3975-
1.0353-
7.0393-
9.9158-
9.0068-
4.6437-
8.2414-
7.2175-
6.6624-4.5299-
3.8861-
5.0437-
4.8296-4.9769-
5.2588-
6.3809-
3.0877-
1.4077-
9.5815-
2
2
2
1
2
1
111
1
1
11
1
1
3
1
1
11
1
1
11
1
1
1
11
1
3
2
23
3
3
3
3
3
33
3
3
33
3
3
2
2
2
- 50 -
FP
A=12 9
A=130
Xe-131m
A=131
A=132
Xe-133mA=133
A=134
1-135
Xe-135m
A=135
A=136
A=137
A=138
A=139
A=14 0A=141
A=142
A=143
A=144
A=145
A=146
A=147
A=14 8
A=14 9
A=150A=151
A=152
A=153
A=154
A=155A=156
A=157
A=15 8
A=159
A=160
US file
1.011337
1.913653
0.046071
3.290794
5.147494
0.19086.762707
7.609406
6.9410
1.0360
6.967573
6.979834
6.052506
5.762451
5.670141
5.815665.336511
4.585776
4.622060
4.547939
3.808983
3.445628
2.592719
2.112485
1.625277
1.273456
0.7993970.530227
0.414787
0.216281
0.141515
0.076033
0.041375
0.018487
0.008619
0.003544
error(%)
6.
6.
1.4
1.0
1.4
2.8
0.5
2.8
2.
2.8
0.7
2.0
0.7
1.4
1.00.7
2.
1.0
0.7
0.7
0.7
0.7
0.7
0.7
1.0
1.0
1.0
1.0
2.
1.0
11.
2.
16.
16.
16.
23.
UK file
6.2464-
1.6760+
3.7135-
3.4381+
4.8484+
1.9713-
6.8441+6.5147+
6.6950+
1.0488+
6.7099+
6.7274+
6.2853+
6.1030+
6.0037+
6.0862+5.8580+
4.7945+
4.7807+
4.5543+
3.9097+
3.5216+
2.6361+
2.2540+
1.6512+
1.2892+
7.9760-
5.5069-
3.5788-
2.3728-
1.2604-
6.7153-
3.4374-
1.7343-
8.3057-
3.2833-
1
0
2
0
0
1
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
1
1
1
1
1
2
2
2
3
3
error
6.0375-
4.2342-
3.3995-
3.1473-
4.4053-
2.0222-6.0022-
5.7792-8.1387-
1.2572-
5.9857-
5.6659-
8.5703-
6.0754-
5.4202-5.4980-5.8322-
7.3957-
5.6021-
4.1453-
3.6825-
3.3323-
113916-
2.5734-
2.9535-
1.2737-
8.0774-5.4589-
4.1342-
2.9085-
3.3532-6.9204-
1.1400-
4.7529-
2.9645-
9.6218-
2
1
3
1
1
2
1
1
1
1
11
1
1
11
2
1
1
1
1
1
1
1
1
1
2
2
2
2
23
2
3
3
4
Table C-l.5: Pu-239 thermal fission
H -
H -
H -
He-
He-
A=
A=
FP
1
2
3
3
4
77
78
US file
0.007235
0.018776
error(%)
11.
23.
UK file
4.0800-
1.3470-
1.4420-
1.4420-
2.0800-7.7041-
2.9291-
3
3
2
2
1
3
2
error
7.0527-
2.8929-
1.1431-
1.1431-9.9813-8.7734-
2.6873-
4
4
3
3
3
4
3
- 51 -
FP
A= 79
A= 80A= 81
A= 82
A= 83
A= 84
Kr-85
A= 85
A= 86
A= 87
A= 88
A= 89
A= 90A= 91
A= 92
A= 93
A= 94
Nb-95m
A= 95
A= 96
A= 97
A= 98
A= 99A=100
A=101A=102
A=103
A=104
A=105
Ru-106
A=106
A=107
A=108
A=109
A=110
A=lllA=112A=113
A=114
A=115
A=116
A=117
A=118
A=119
A=120
A=121A=122A=123
A=124
A=125
US file
0.043651
0.093888
0.183643
0.229687
0.296793
0.480359
0.1227
0.574068
0.766201
1.003923
1.329789
1.722836
2.104298
2.4865003.009177
3.797575
4.321833
0.04831
4.818517
4.893751
5.414114
5.830892
6.211806
6.7746216.019171
6.126339
6.994895
6.094829
5.643815
4.3500
4.350214
3.330057
2.1639561.477898
0.645132
0.295993
0.128506
0.081664
0.060254
0.042600
0.050678
0.044459
0.032488
0.032249
0.0305850.037808
0.044695
0.044120
0.078717
0.111659
error
2.
23.
16.
23.
0.5
1.0
1.4
0.35
0.5
0.5
1.0
2.
2.
1.
0.7
0.7
1.0
2.
1.0
1.
1.0
1.0
1.4
1.4
1.4
1.4
2.
1.0
2.
2.
2.
4.
4.4.
6.
2.
2.
2.8
2.8
6.
8.
8.
8.
8.
11.
8.
8.
16.
11.
8.
UK file
5.6471-
1.0501-
1.8859-
2.4865-
2.8224-
4.7244-
1.3612-5.9322-
7.6965-
9.5813-
1.2967+
1.6974+
1.9931+
2.4523+3.0073+
3.8749+
4.3690+
5.5193-
4.9652+
4.9436+
5.2279+
5.9339+
6.1803+
6.8555+
6.1756+
6.0734+
6.9115+
6.0651+
5.7592+
4.1843+
4.1870+
3.1717+
2.0535+1.7180+
6.2441-
3.0742-
1.2821-8.1038-
5.3920-
3.6415-
4.5734-
4.5731-
4.5662-
4.8757-
4.3373-
5.5220-6.9715-
8.9202-
1.2835-
1.1731-
2
1
1
1
1
1
1
1
1
1
0
0
0
0
0
0
0
2
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
1
1
1
2
2
2
2
2
2
2
2
2
2
2
1
1
error
8.3107-
1.5309-
2.5226-
3.4488-
9.5404-
1.9541-
6.4821-
2.4855-
1.6597-
4.7591-
3.6448-
3.6418-
4.5830-
1.9244-1.3285-
1.1842-
1.1624-
1.4113-
9.8005-
1.4430-
2.2972-
3.8151-
1.2324-4.4710-
2.0719-2.9261-
1.7076-
2.0474-
1.4688-
8.5134-
8.3230-
1.2795-
8.7922-1.3427-
3.1242-
7.0801-
7.3268-
3.9137-
2.6994-
1.8402-
2.2895-
2.2896-
3.2049-
3.4320-
5.3339-8.1445-
3.4773-
1.3069-
6.3339-
1.3905-
3
2
2
2
3
2
3
2
2
2
2
2
2
1
1
1
1
3
2
1
1
1
1
1
1
1
1
1
1
2
2
1
2
1
2
3
3
3
3
3
3
3
3
3
3
3
3
2
3
2
- 52 -
FP
A=126
A=127
A=12 8
A=129
A=130
Xe-131m
A=131
Te-132
A=132
Xe-133m
A=133
A=134
1 = 135
Xe-135m
Xe-135
A=135
A=136
Cs-137
A=137
A=13 8
A=13 9
Ba-140
A=14 0
A=141
A=142
A=143
A=144
A=145
A=14 6
A=147
A=148
A=149A=150A=151
A=152
A=153
A=154
A=155
A=156
A=157
A=158
A=159
A=160
US file
0.2023240.506296
0.734121
1.371454
2.361688
0.054019
3.856439
5.1390
5.406858
0.2346
7.0164667.676881
6.5420
1.7140
7.66080
7.621001
7.143924
6.6070
6.613842
6.124533
5.637200
5.3550
5.364788
5.246968
4.928967
4.413261
3.739785
2.986310
2.458146
2.002981
1.642120
1.216561
0.9674590.738426
0.576317
0.361259
0.259788
0.165724
0.124018
0.074152
0.0414390.020653
0.009681
error
6.
6.
11.
4.
8.
2.
0.5
2.
0.5
16.
0.5
0.5
2.8
32.
1.0
0.7
1.0
0.5
0.5
1.0
2.8
1.4
1.0
2.
0.5
0.5
0.35
0.35
0.35
1.0
0.5
0.7
0.5
0.7
1.0
6.
1.4
11.
4.
6.
16.
6.
16.
UK file
3.1550-4.6206-
8.3462-
1.4105+
2.8949+4.0313-
3.7294+
5.1113+
5.2915+
2.1087-
6.7685+
6.9055+
6.3506+
1.7219+
7.3928+
7.4073+
6.8649+
6.7235+
6.7290+
6.1310+
5.9952+5.3187+
5.3300+
5.2068+
4.9652+
4.4787+
3.7486+
3.0322+
2.4907+
2.0408+
1.6789+
1.2630+9.7568-7.7758-
6.0786-
3.9953-
2.7987-
1.5937-
1.1457-
7.5581-
4.0766-
2.1369-
1.0411-
1
1
1
0
0
2
0
0
0
1
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
1
1
1
1
1
1
1
2
22
2
error
4.5039-2.3722-
4.9365-
6.7241-
2.6076-
7.9511-
5.3547-
1.1772-
1.0341-
6.9941-
1.3091-2.2748-
3.6663-
1.8711-
1.7430-
1.7495-
1.8881-
5.3918-
1.4120-
1.4121-1.1654-1.0380-
1.0388-
1.7430-
1.0080-8.7227-
7.3472-
5.9799-
4.9296-
4.1702-
3.3347-
2.7674-1.9447-1.7848-
1.6369-
5.7096-
1.1462-
2.3370-
4.4704-
7.5919-
6.1504-
1.9363-1.5648-
2
2
2
2
1
4
2
1
1
3
1
1
1
1
1
11
1
1
1
1
1
1
1
1
2
2
2
2
2
2
2
2
2
2
2
2
2
3
3
3
3
3
- 53 -
Table C-1.6: Pu-241 thermal fission
FP
H - 3
He- 3
He- 4A= 77A= 78A= 79A= 80
A= 81
A= 82
A= 83
A= 84
Kr- 8 5
A= 85
A= 86
A= 87
A= 88A= 8 9
A= 90
A= 91A= 92A= 93
A= 94
Nb-95m
A= 95
A= 96
A= 97
A= 98
A= 99
A=100
A=101A=102
A=103
A=104
A=105
A=106
A=107
A=108
A=109A=110
A=lllA=112A=113A=114
A=115
A=116
A=117
A=118
US file
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
1.
1.1.
2.
2.
3.
0.
3.
4.
4.
5.
5.
6.
6.
6.
6.
7.
6.
6.
4.
3.
2.
1.
0.
0.
0.
0.
0.
0.
0.
0.
001896
011521
014959029235
062121
136745
201544
351325
083114
406488
594552
752828
990303
233109
535820
864133
308494
978050
391152
039258
925621
401147
801799
035685
961885
254494
231942655272
776879
179518
074350
103987
886332
769599587597
325114585511
218486
151924
071086
038087
027787
023626
023157
error
23.
16.
16.
16.
16.
8.
1.4
2.
2.8
1.4
2.
2.
1.42.8
1.4
1.4
1.4
1.4
1.4
2.8
1.4
1.4
1.4
2.
2.
2.
2.
2.
2.8
2.
2.8
2.
8.
8.
4.8.
2.8
2.8
4.
23.
11.
32.
11.
32.
UK file
1.4100-
1.4100-
2.0150-
4.9654-
3.2269-
9.9117-2.4543-
5.4388-
1.1250-
1.9983-
3.5783-
8.5409-
3.9504-
6.1450-
7.4639-
1.0043+
1.2301+1.5679+
1.7770+
2.3477+
3.0409+
3.3712+
4.4301-
3.9908+
4.3143+
4.6503+
5.1121+
5.6475+
6.8781+
5.7867+6.2799+
6.8912+
6.8932+
5.9518+
6.1356+
4.9371+
3.9155+
2.7362+1.3638+
5.8703-
1.9329-
1.8491-
1.9556-
1.6397-
1.2504-
8.9845-
6.4049-
2
2
1
4
3
3
2
2
1
1
1
2
1
1
1
0
0
0
0
0
0
0
2
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
1
1
11
1
1
2
2
error
2.4373-
2.4373-
2.8773-
1.1775-
1.6954-
5.0874-1.2584-
2.7624-
5.5327-
2.7036-
4.7347-
1.2529-
5.5741-
7.9957-
1.1430-1.2671-
1.5814-
2.0188-
3.1347-
3.6721-
3.6667-
4.3095-
5.8733-
5.1574-
5.5549-
7.2208-
6.7883-
7.4853-
9.0679-
7.7836-8.3652-
9.1332-
8.7550-
7.7390-
7.8339-
6.8310-
5.2877-
3.6673-6.2801-
2.6784-
4.0689-
5.3551-
1.0210-
8.2339-
6.5970-
4.7501-
3.3911-
3
3
2
4
3
3
2
2
2
2
2
2
2
21
11
1
1
1
1
1
2
1
1
1
1
1
1
11
1
1
1
1
1
1
1
1
1
2
2
1
2
2
2
2
- 54 -
FP
A=119
A=120
A=121
A=122A=123A=124
A=125
A=126
A=127
A=128
A=129
A=130
Xe-131m
A=131
Te-132
A=132Xe-133m
A=133
A=13 4
I -135Xe-13 5m
Xe-135
A=135
A=136
A=137
A=138
A=139
A=140
A=141
A=142
A=143
A=144
A=145
A=146
A=147
A=148A=149A=150
A=151
A=152
A=15 3
A=154
A=155
A=156
A=157
A=158
A=159
A=160A=161
A=162
US file
0.023156
0.025623
0.025882
0.0258820.0267040.032352
0.046901
0.082238
0.232387
0.379232
0.819252
1.818826
0.043412
3.100837
4.5030
4.564343
0.1944
6.729190
7.917365
6.94301.182
7.1701
7.170771
7.105131
6.650911
6.605149
6.217390
5.766685
4.905772
4.746982
4.577993
4.227384
3.262911
2.766456
2.284949
1.9321031.4740761.209434
0.913021
0.717632
0.540584
0.379114
0.241414
0.172125
0.135369
0.092244
0.048030
0.020499
0.008468
error
32.
23.
32.
32.32.
32.8.
23.
4.
23.
23.
11.
4.
1.4
2.8
1.44.
0.7
1.4
2.816.
2.1.0
1.4
0.7
1.0
2.1.4
1.4
1.0
0.7
0.7
1.0
0.7
1.4
0.7
1.41.0
1.4
1.4
4.
2.
8.
2.8
4.
23.
4.
23.
4.
UK file
5.1725-
5.8283-
9.2000-
1.0580-1.3751-1.8475-
2.5873-
3.7349-
5.6292-
8.2962-
1.3333+
2.0717+
3.2775-
3.0344+
4.4216+
4.4383+1.8581-
6.4310+
7.4213+
6.8359+1.1840+
7.0113+
7.0122+
6.7786+
6.4249+
6.5165+
6.3815+
5.8320+
4.8883+
4.6788+
4.3022+
3.9623+
2.9817+
2.4878+
2.1204+
1.7574+1.3964+1.1019+
8.4426-
7.1598-
5.0477-
4.0419-
3.9721-
3.1887-
2.5137-
1.9214-
1.3487-
1.0408-
7.3399-
5.0974-
2
2
2
11
11
1
1
1
0
0
2
0
0
0
1
0
0
00
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
1
1
1
1
1
1
1
1
11
2
2
error
2.2521-
2.4206-
3.2331-
3.7177-4.8466-
6.5208-
9.1843-
1.3356-
2.0274-
2.9552-
4.6024-
6.8752-
4.4614-
4.1305-
5.9627-
5.9953-
2.3936-
8.4628-
9.5689-
8.8839-1.6244-
8.9915-
9.1416-
9.6451-
8.2675-
8.3863-
1.6076+
7.6529-
7.7716-
6.1964-
5.7116-
5.3861-
4.1958-
3.5415-
3.7956-
2.4818-
1.9839-1.5604-
1.1899-
1.0067-
1.3611-
6.9870-
1.5862-
1.2409-
9.6873-
7.2121-
5.0895-
3.7957-
2.9533-
1.8554-
2
2
2
2
22
21
1
1
1
1
3
1
1
1
2
1
1
11
1
1
1
1
1
01
1
1
1
1
1
1
1
111
1
1
1
2
11
2
2
2
22
2
- 55 -
C-2: Selected independent fission product yields
The table below summarises the yield values (and types) which are significantand included in Tables C-2.1 to C-2.6.
FP
Kr-82
Kr-8 5
Nb-95m
Nb-95
Mo-9 6
Xe-130
Xe-133m
Xe-133
Cs-134
Xe-135m
Xe-135
Nd-144
Sm-150
Eu-154
Th-232
c
i
c
i
i
U-233
c
i
c
c
i
i
i
i
i
c
c
i
U-235
c
i
c
c
i
i
i
i
c
U238
i
i
i
i
i
Pu-239
c
i
i
i
c
c
i
i
i
i
i
c
c
i
Pu-241
c
i
c
i
i
i
i
Description of table entries:
Type: i independent yield of fission product is listed
c cumulative yield of fission product is listed when shielded from betadecay by a stable or long lived precursor; the yield value given is thesum of the independent yields of the nuclide listed and it's short livedprecursors which are also shielded (eg.: the cumulative field of Kr-82is the sum of independent yields of Br-82m, Br-82 and Kr-82, all shieldedby stable Se-82).
Only those yield values are listed that exceed 0.01% of the correspondingchain yields in one of the files. According to this criterion, the independentyields of the following fission products, although requested by safeguards experts,are insignificant and not included in any of the tables: Mo-92, 94, Xe-128, 129, Nd-142, Pm-148m,148, Sm-148, Eu-151, Eu-152.
Source of data:
US file: ENDF/B-6 Fission Yield File.UK file: R.W. Mills,: "UKFY3",the the latest update of UK library of
independent and cumulative fission product yields, in ENDF-6 format(1996) .
The file UKFY3 contains also several other tables of fission yield data anddiscrepances which are available from the author or the Data Centers.Both the USfile and the UK file are available on magnetic tape from the Data Centers.
- 56 -
Table C-2.1: Th-232 fast fission
FP
Kr- 82
Kr- 85
Mo- 96
Xe-135m
Xe-135
Type
c
i
c
i
i
US file%/fission
9.8798-
9.9498-
1.7800-
7.5508-
2.6529-
5
4
4
3
3
errorabs
6.3231-5
6.3679-4
8.0100-5
4.8325-3
1.6979-3
UK file%/fission
8.4515-
1.5502-
5.8294-
1.1571-
4.1357-
5
3
6
2
3
errorabs
6.3502-
1.0902-
5.2087-
8.9833-
3.2107-
5
3
6
3
3
Table C-2.2: U-233 thermal fission
FP
Kr- 82
Kr- 85
Mo- 9 6
Xe-130
Xe-133mXe-133
Cs-134
Xe-135m
Xe-135
Nd-144Sm-150
Eu-154
Type
c
i
c
c
i
i
i
i
i*
c
i
US file%/fission
8.2998-
9.5576-
5.5859-
2.5969-
4.1321-1.4667-
1.3400-
0.8063+
0.4206+
2.7558-
4.3699-1.0400-
4
2
3
3
2
2
4
0
0
4
4
6
errorabs
1.3280-4
2.1982-2
3.5750-3
7.2714-5
2.6445-25.8667-4
8.5758-5
0.5160+0
4.6271-2
1.5969-42.7967-4
6.6558-7
UK file%/fission
7.0101-
7.4844-
8.1389-
3.0718-
2.7917-
1.1564-9.8285-
8.2264-
3.4076-
1.0683-
1.1306-3.8653-
3
2
3
3
2
2
4
1
1
3
3
6
errorabs
2.6386-
2.8763-
3.2030-
1.2114-
1.1059-
4.5810-3.7408-
2.5306-
1.0483-
3.7902-
4.7102-
1.7776-
3
2
3
3
2
3
4
1
1
4
4
6
*) Sum of Pr-144 + Nd-144 independent yields.
Table C-2.3: U-235 thermal fission
FP
Kr- 82
Kr- 85
Mo- 96
Xe-130
Xe-133mXe-133Xe-135mXe-135
Sm-150
Type
c
i
c
c
i
i
i
i
c
US fil«a%/fission
5.4696-
2.5533-
5.4396-
2.2198-
1.8859-6.6595-0.1781+
7.8513-
2.9998-
5
2
4
4
3
4
0
2
5
errorabs
6.0166-6
4.0853-3
3.4813-4
3.5517-5
1.2070-3
3.9957-51.0687-2
4.7108-3
1.9199-5
UK file%/fission
2.8024-
5.1951-
4.1961-
3.5329-
1.0563-
4.3753-1.6532-
6.8480-
6.1426-
4
3
4
5
3
4
1
2
5
errorabs
9.9192-
1.9226-
1.5231-
1.3015-
3.8000-1.5743-5.7784-
2.3936-
2.2478-
5
3
4
5
4
4
2
2
5
- 57 -
Table C-2.4: U-238 fast fission
FP
Kr- 85
Xe-133m
Xe-133
Xe-135mXe-135
Type
i
i
i
i
i
US file%/fission
1.9900-
1.2210-
4.1800-
1.5710-1.1154-
4
3
4
2
2
errorabs
1.2736-4
7.8145-4
2.6752-4
1.0055-27.1386-3
UK file%/fission
4.8698-
1.9489-
6.9656-
1.1101-3.9677-
5
5
6
2
3
errorabs
2.8886-
1.1543-
4.1257-
6.8002-2.4304-
5
5
6
2
3
Table C-2.5: Pu-239 thermal fission
FP
Kr- 82
Kr- 85
Nb- 95m
Nb- 95
Mo- 96
Xe-130
Xe-133m
Xe-133
Cs-134
Xe-135m
Xe-135
Nd-144
Sm-150
Eu-154
Type
c
i
i
i
c
c
i
i
i
i
i*
c
i
US file%/fission
1.2890-
1.0026-
1.3200-
5.6499-
3.6090-
4.6939-
3.3799-
9.4479-
3.3500-
0.7523+
0.3141+
3.6574-
1.1520-1.4000-
3
2
4
4
3
3
2
3
4
0
0
4
3
5
errorabs
2.5780-5
6.4166-3
8.4479-4
3.6160-42.3097-3
6.5715-5
2.1631-2
1.0393-3
2.1440-4
0.4815+0
1.2565-2
2.1186-4
7.3727-48.9599-6
UK fil<a%/fission
1.8558-
1.2328-
8.4180-
3.6406-
5.0806-
1.7210-
1.6608-
6.8793-
5.7351-
7.3758-
3.0552-
1.2372-2.2585-
2.5155-
3
2
5
4
3
3
2
3
4
1
1
3
3
5
errorabs
6.8191-
4.3574-
3.0673-
1.3266-1.8108-
5.1997-
6.0289-
2.4973-
2.0511-
2.3517-
9.7416-
7.3020-
7.8736-9.1668-
4
3
5
4
3
4
3
3
4
1
2
4
4
6
Sum of Pr-144 + Nd-144 independent yields.
Table C-2.6: Pu-241 fast fission
FP
Kr- 82Kr- 85Mo- 9 6
Xe-133m
Xe-133
Xe-135mXe-135
Type
c
i
c
iii
i
US filB%/fission
3.2300-
2.3780-1.2326-
6.1400-
2.5100-
0.1614+6.5501-
43
2
4
4
0
2
errorabs
2.0672-41.5219-3
5.5467-3
3.9296-4
1.6064-4
0.1033+0
5.2401-3
UK file%/fission
1.1859-1.5451-
3.3488-
6.1715-
2.5564-
1.2442-
5.1539-
4
3
4
4
4
1
2
errorabs
9.0654-1.0057-
2.2303-
4.0381-
1.6727-
8.2420-3.4140-
5
3
4
4
4
2
2
Nuclear Data SectionInternational Atomic Energy AgencyP.O. Box 100A-1400 ViennaAustria
telephone: (43-1)2060-21710online: TELNET or FTP: iaeand.iaea.or.atusername: IAEANDS for interactive Nuclear Data Information Systemusername: ANONYMOUS for FTP file transferusername: FENDL for FTP file transfer of FENDL-1 files, FENDL2 for FENDL-2 filesFor users with web-browsers: http://www-nds.iaea.or.at