HANDBOOK OF NUCLEAR DATA FOR SAFEGUARDS

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

resonance integrals 39

Section C: Fission product yields 42

C-l: Chain yields and selected cumulative yields 42C-2: Selected independent fission product yields 55

- 4 -

FOREWORD

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]

For former USSR countries:

Centr po Jadernym DannymFiziko-Energeticheskij InstitutPloschad Bondarenko249020 Obninsk, Kaluga RegionRUSSIAINTERNET: [email protected]

For all other countries:

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. )


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.


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


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.

Table A-2

nuclide

90-Th-228

90-Th-229

90-Th-230

90-Th-232

91-Pa-231

energy(keV)

5340.365423.15

4797.84814.64838.04845.34901.04967.54978.55053.0

4438.44479.84620.54687.0

3830.03947.24012.3

4508.04566.04599.04632.04643.04681.04713.04736.04795.04853.04934.04951.34975.04986.05013.85028.45032.05058.6

+

±

++±+±±±±

±±±±

+±±

±

+±++±±+±+±±±+±+±±

0.150.22

1.21.22.01.21.21.21.22.0

1.61.61.51.5

10.02.01.4

2.02.02.02.02.02.02.00.82.02.02.01.42.02.01.41.02.01.5

emission(percent

27.272.2

1.509.305.0056.2010.205.973.176.60

0.0300.12

23.4076.3

0.05922.177.8

0.0030.0080.0150.10.11.501.008.40.041.43.00

22.80.41.4

25.420.02.511.0

probabi1i typer decay)

± 1.0± 1.1

± 0.20± 0.08± 0.20± 0.20± 0.08± 0.06± 0.04± 0.10

+ 0.015

± 0.10± 0.3

± 0.01± 1.4± 1.4

- 11 -

nuelide

92-U-232

92-U-233

92-U-234

92-U-235

92-U-236

92-U-238

93-Np-237

94-PU-236

94-PU-238

94-PU-239

energy(k

5139.05263.365320.12

4729.24783.54824.2

4603.54722.44774.6

4150.04214.74323.04325.84359.64366.14378.64397.84414.04435.04502.04556.04596.4

4332.04445.04494.0

4038.04151.04198.0

4581.04598.64639.44664.04766.04771.04788.04803.34817.3

5613.615721.05767.66

5207.765357.915456.35499.03

4829.234866.764870.234911.544934.854962.694987.98

eV)

±++

+

±+

+

±+

+++++++++++++

+++

++

±

+

±+++++

±+

+±+

±++

±

+++++++

1.50.090.14

1.21.21.2

1.51.41.4

5.01.91.31.31.32.01.31.34.05.02.02.01.3

8.05.03.0

5.05.03.0

2.02.02.02.01.51.51.52.02.0

0.090.100.08

0.200.200.300.20

0.140.140.140.140.140.140.14

emission(percent

0.331.768.0

1.6113.284.4

0.228.4271.38

0.95.74.40.210.24

17.00.16

55.02.10.71.74.25.0

0.2626.074.0

0.07821.079.0

0.400.346.183.328.0

25.047.01.5602.5

0.1830.669.3

0.0030.105

28.9870.91

0.003730.00210.000700.00310.00410.0060.0052

probabilityper decay)

+++

++

+

++

+

±±±±±±±±

+++

+++

+++

+++±+++

+

+±

+±+

+

0.020.40.4

0.20.5

0.010.090.16

0.20.60.50.040.072.00.163.00.1

0.20.30.5

0.014.04.0

0.0123.03.0

0.040.040.120.13.06.09.0

0.4

0.50.5

0.0050.10.1

0.003

- 12 -

nudide

94-PU-239

94-PU-240

94-PU-241

94-PU-242

95-Am-241

95-Am-242m

95-Am-243

96-Cm-242

energy(JceV)

4988.655008.545029.375055.195076.135105.55111.205144.35156.505156.59

4863.605021.235123.685168.17

4784.4798.4853.44896.44972.4998.5042.5054.

4598.54754.64856.24900.5

5322.05388.235442.805485.565511.475544.5

5062.95081.25087.15141.65206.85246.35248.65271.15313.15365.85408.2

4695.04930.04946.05088.05113.05181.05233.35275.35321.05349.4

5814.05971.06069.426112.72

±+±+±+++++

++

++

++++++±+

++++

++++++

++±+++±++++

+++±+±+

±±+

++

±+

0.140.140.140.140.140.80.20.80.140.14

0.150.150.230.15

5.3.1.21.22.2.2.2.

1.61.31.21.2

1.00.130.130.120.131.6

0.50.50.50.50.50.90.50.51.00.50.5

3.03.03.03.01.01.01.01.01.02.3

2.03.00.120.08

emission probability(percent per decay)

0.00220.01820.00510.0300.03611.50.01515.10.030

73.3

0.001080.08520

27.1072.80

0.0000050. 0000290.0002920.002010.0000310.0000100.000025

+++±+

+

++

+++++±

0.0000025

0.001300.098

22.478.0

0.0151.613.084.50.220.34

0.001010.0001380.0008720.026710.4120.0005050.0001840.0039470.0031670.0053700.004774

0.001700.00020.00030.0040.0051.1011.087.40.1200.160

0.00310.035

25.074.0

++±

+

±++++

+

±±±+

+

+++

0.0040.0040.80.0150.8

0.8

0.10.1

0.0000020.0000030.0000050.000020.0000060.000001

0.0172.03.0

0.0050.20.61.00.030.05

0.011

0.40.40.0200.020

0.00050.0020.50.5

- 13 -

nuclide

96-Cm-243

96-Cm-244

98-Cf-252

53165323533255235537556855755582558755935609561256235639564656825686571357425785587659075991601060586066

5513566457625804

597660756118

energy(iceV)

.1

.2

.8

.

.0

.2

.

.70

.82

.50

.77

.24

++±+++++++++±±±++±++++++++

++++

++±

3.3.3.3.3.3.3.3.3.3.3.3.5.3.3.3.3.5.

0.90.93.3.

1.53.

1.01.7

3.3.0.030.05

0.060.110.04

emission(percent

0.0009980.0029930.0029930.0019950.0019950.0069830.0069830.0089780.019950.0099760.0050.029930.059860.13970.029930.19951.59620.020

11.572.70.59860.099765.690.99764.71.50

0.0035000.0221

23.6076.40

0.2315.281.6

probabilityper

+

++++

+

±+

±±

±±+

0

0001

0

00

00

000

decay)

.005

.0005

.020

.5

.0

.20

.3

.20

.20

.20

.04

.3

.3

- 14 -

A-3: Gamma ray energies and emission probabilities

The table does not contain Y~rays from daughter products in equilibrium.


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).

Table A-3

nuclide

81-T1-208

82-Pb-212

83-Bi-212

86-Rn-220

88-Ra-224

90-Th-228

90-Th-229

energy(k

252.6277.35510.80583.191763.13860.37

1093.12614.6

115.176238.632300.087

288.07327.96452.83727.330785.42893.408

1078.621620.735

549.7

241.0

84.40131.62166.37215.94

56.5294.73107.11110.33

BV

+

±+±±±±±

++

±

+++++±±±

±

±

+++±

+

±±±

)

0.30.060.080.0020.080.080.10.1

0.0070.0020.010

0.070.100.100.0090.060.0050.100.010

0.5

0.1

0.050.200.200.08

0.010.020.010.01

emission(percent

0.8076.4

22.885.11.89

12.520.45

99.83

0.643.53.25

0.310.120.366.641.10.3810.5741.49

0.114

4.05

1.220.1270.1070.26

0.3120.4650.8090.128


+±+±±±++

+++

+

±++++++

+

±

+

+±±

+

±±±

0.0110.060.30.60.060.120.060.17

0.020.40.04

0.040.0080. 040.090.020.0140.0150.06

0.017

0.04

0.030.0070.0040.01

0.0070.0080.0130.003

rel err

( 1-4 )( 0.94)( 1-3 )( 0.71)( 3.2 )( 0.96)(10. )( 0.17)

( 3.3 )( 0.92)( 1-2 )

(10. )( 6.7 )(10. )( 1.4 )( 1-8 )( 3.7 )( 2.6 )( 4.0 )

(10. )

( 0.99)

( 2.5 )( 5.5 )( 3.7 )( 3.9 )

( 2.2 )( 1.7 )( 1.6 )( 2.3 )

- 15 -

nuclide

90-Th-229

90-Th-230

90-Th-231

90-Th-232

90-Th-233

90-Th-234

91-Pa-231

123.124.131.136.142.148.156.179.193.204.210.

67.143.186.253.

58.72.81.82.84.89.99.

102.124.134.135.217.

59.126.

29.86.88.94.

162.169.170.190.194.359.441.447.459.490.499.595.669.764.890.

63.92.92.

112.

255.260.273.277.283.300.

energy(keV)

1960939909604176509698

672872053729

570751228087214952782709140366494

365006851754909072802841

29388081

903237322690069

+++++±+±±++

±+++

+±++++++++++

++

++++++++++++

+±+++±+

±±±±

±++±±+

0.010.050.010.0040.010.20.010.010.0040.010.1

0.0020.0040.0040.010

0.0030.0030.0030.0030.0030.020.0040.0030.0170.020.0110.03

1.5.

0.040.050.20.050.10.20.30.080.050.20.30.30.20.30.30.20.20.40.5

0.020.010.020.05

0.040.10.1170.0130.0130.008

emission

01010110403

0000

000060000000

00

2200000000001000000

4220

000012

(percent

.197

.449

.327

.171

.401

.091

.237

.215

.41

.595

.18

.376

.0486

.0088

.0111

.5

.26

.85

.37

.71

.94

.12

.4

.06

.025

.084

.037

.19

.043

.5

.7

.3

.8

.32

.34

.13

.13

.16

.12

.23

.15

.4

.17

.21

.16

.68

.12

.14

.47

.60

.56

.256

.107

.182

.059

.069

.65

.41

probabilityper

+

+++++±+++±

++±+

±±+++++

±++±+

±+++

±+±±+±

0.0.0.0.0.0.0.0.0.0.0.

0.0.0.0.

0.0.0.0.0.0.0.0.0.0.0.0.

0.0.0.0.

0.0.0.0.0.0.

decay)

003020050160060150180040600904

043005100090012

050203021080102003005007001

885352054

0030050020020406

rel

( 1-( 1.( 1.( 1.( 1.( 1.( 1.( 1.( 1.( 1.{ 1.

(10.(10.(10.(10.

(10.( 7.( 3.( 5.( I-( 0.( 0.( 5.( 5.(20.( 8.( 2.

(20.(20.(20.(20.

( 2.( 2.( 3.( 2.( 2.( 2.

err

54545459453

75458800

37

))))

8 )8 )4 )9 )4 )5 )

)))))))))))

))))

)))))))

- 16 -

nudide

91-Pa-231

91-Pa-233

92-U -232

92-U -233

92-U -234

92-U -235

92-U -236

92-U -237

energy(keV

302.669330.057340.77354.474357.16

75.2886.59103.86271.48300.12311.98340.50375.45398.62415.76

57.78129.08270.2327.9

54.699118.968120.816135.3146.345164.522208.171245.345291.354317.2320.541

53.20120.90

109.16140.76143.76163.33182.61185.715194.94202.11205.311221.38

49.369112.750

51.0159.54364.83164.61208.005221.80234.40267.54332.36335.38368.59370.94

+

±±+±

±±±±++±±+±

±±±±

+

±±

++±+±

±

±

±

++±±±±±+±±

+

±

+

±±±±++±++±±

I0.0060.0150.070.0750.07

0.010.010.020.080.030.030.040.040.080.04

0.050.050.20.2

0.0010.0020.001

0.0020.0020.0020.0020.004

0.005

0.020.02

0.020.040.020.020.050.0050.010.020.0100.02

0.0090.015

0.030.0150.020.020.0230.040.040.040.040.040.040.04

emission(percent

2.471.360.1780.0970.169

1.321.970.870.326.63

38.634.500.681.411.74

0.2000.06820.003160.00283

0.01820.004060.003320.002320.006570.006230.002290.003620.005370.007760.00290

0.1230.0342

1.540.2210.965.080.34

57.20.631.085.010.12

0.0780.019

0.2034.51.311.87

21.60.02050.02050.7301.210.0970.0420.11


++±±±

+

±+±±+±+±±

±±±±

±

±+±+±+

±±±±

+

±

++

±+±+±+

±±

±±

±++±±±+++±

±

0.060.030.0040.0030.005

0.040.120.030.010.060.390.050.010.020.02

0.0020.00040.000050.00006

0.00030.000040.000030.000020.000060.000050.000030.000030.000050.000070.00003

0.0020.0005

0.050.020.080.040.020.50.010.020.050.01

0.0080.005

0.090.80.030.050.50.00080.00080.0180.030.0030.0020.004

rel err

( 2.4 )( 2.2 )( 2.3 )( 3.1 )( 3.0 )

( 3.0 )( 6.1 )( 3.5 )( 3.1 )( 0.9 )( 1.0 )( 1.1 )( 1.5 )( 1.4 )( 1.2 )

( 1.0 )( 0.59)( 1.6 )( 2.1 )

( 1.7 )( 0.99)( 0.9 )( 0.86)( 0.91)( 0.8 )( 1.3 )( 0.83)( 0.93)( 0.9 )( 1.0 )

( 1.6 )( 1.5 )

( 3.3 )(10. )( 0.73)( 0.79)( 5.9 )( 0.87)( 1.6 )( 1.9 )( 1.0 )( 8.3 )

(10. )(30. )

(50. )( 2.3 )( 2.3 )( 2.7 )( 2.3 )( 3.9 )( 3.9 )( 2.5 )( 2.5 )( 3.1 )( 4.8 )( 3.6 )

- 17 -

nudide

92-U -238

92-U -239

93-Np-236m

93-Np-237

93-Np-238

93-Np-239

94-PU-236

94-PU-238

94-PU-239

49

4374100104.160.

44.538.642.687.

46.57.86.88.117.131.134.143.151.155.169.195.212.238.

101.119.882.918.923.936.941.962.984.

1025.1028.

61.106.209.226.228.277 .285.315.334.

47.109.165.515.563.645.

43.99.

152.

51.56.

123.

energy(JteV)

55

533664

2

6093361

53155030468104232083722170964150

99636998613877458754

46012375342183599460880310

60

62

498853720

62482562

±

±±

±

±±±±

±±±±±

±±

±±

±±±±±±±±±±±

±±±±±±±±±

±±±

±±±

0

00

0.

0.0.0.0.

0.0.0.0.0.

0.0.

0.0.

0.0.0.0.0.0.0.0.0.0.0.

0.0.0.0.0.0.0.0.0.

0.0.0.

0.0.0.

06

001001

6

1150910

040402016030

02504

020025

031030402060503020202

00200200208001001002003002

001003002

00100305

emission

0

44807

27

0000

00

1200000000000

00002000

279

20

12730

1114012

000000

000

00(1

probabi1i ty(percent per

.064

.16

.1

.5

.5

.6

.0110

.011

.92

.25

.106

.382

.3

.138

.173

.086

.071

.432

.234

.092

.071

.185

.151

.059

.27

.108

.87

.59

.86

.40

.54

.70

.8

.6

.3

.29

.2

.42

.28

.27

.38

.79

.60

.07

.069

.012

.00066

.00017

.00010

.00024

.0395

.00735

.000937

.0271

.00113097

±

+++±±

+

±±±

+

±±±±±±±±±±±±±

±±±±±±±±±±±

±±±±±±±±±

±±±±+±

±±±

±±±

0.

0.1.0.0.0.

0.0.0.0.

0.0.0.0.0.0.0.0.0.0.0.0.0.0.

0.0.0.0.0.0.0.0.0.0.0.

0.0.0.0.0.0.0.0.0.

0.0.0.0.0.0.

0.0.0.

0.0.0.

decay)

008

11

126

00020010602

006Oil2003003002002008004002001002002001

01006030209010202858

02405021821020303

0210040002000050000300008

000800008000010

000500002521) E-05

rel

(10

( 2( 2(20( 2( 2

( 1(10( 6( 8.

( 5.( 2.( 1.( 2.( 1.( 2.( 2.( 1.( 1.( 2.( 1.( 1.( 1.( 1-

( 3.( 5.( 3.( 3.( 3.( 2.( 3.( 2.( 2.( 5.( 3.

( 1.( 1-( 1.( 7.( 1.( 1.( 2.( 1.( 1.

(30.(30.(30.(30.(30.(30.

( 2.( 1-( 1.

( 1.( 2.(10.

err

)

6 )1 )

)7 )2 )

8 ))

5 )0 )

7 )9 )6 )2 )7 )3 )8 )9 )7 )2 )4 )1 )3 )7 )

7 )6 )5 )4 )2 )5 >7 )9 )9 )2 )9 )

6 )5 )5 )1 )6 )5 )5 )9 )5 )

)

))))

)

0 )1 )1 )

9 )2 )

)

- 18 -

nuclide

94-PU-239

94-PU-240

94-PU-241

94-PU-242

95-Am-241

energy(k

124.51125.21129.296141.657144.201146.094161.482171.393179.220188.23189.360195.679203.550255.384297.46311.78332.845341.502345.013375.054380.191382.698392.914413.713422.598445.81451.481481.78639.99645.98651.79658.63718.0769.19

45.242104.235160.307

77.10103.680148.567159.955

44.915103.50158.80

59.53798.97

102.98123.01125.30146.55164.69169.56208.01322.52332.35335.37368.65662.40

eV

+±±±±±±±±±±±±+±±+±+±+±±+±++±±±±±±±

±±±

±±±±

+±

+±±+±+±±±±+±±

±

>

0.030.100.0010.0200.0030.0060.0210.0060.0120.100.0100.0080.0050.0150.030.040.0050.0190.0040.0030.0060.0160.0140.0050.0190.100.0100.120.100.030.100.150.50.04

0.0030.0050.003

0.100.0050.0100.020

0.0130.040.08

0.0010.020.020.020.020.030.040.030.030.030.030.030.030.02

emission(percent

(6.13(7.110.00631(3.20.0003040.0001190.0001230.000110(6.6(1.09(8.30.0001070.000569(8.0(4.98(2.580.000494(6.620.0005560.0015540.0003050.0002590.0005530.0014660.000122(8.80.000189(4.6(8.7(1.52(6.6(9.7(2.8(1.19

0.04470.007140.000402

(2.070.0001020.000186(6.58

0.03730.002550.00030

35.90.0200.01960.0010.00410.00046(7.20.0001720.000790.000150.000150.0004950.000220.00036


+±±+±±±±±±±±±±±±++±±+±±+++++±±±±±±

+±±

+±±±

±±±

+

±±++±++±±±+±

±

0.22) E-050.2) E-050.000060.09) E-050.0000040.0000030.0000020.0000020.1) E-050.11) E-050.1) E-050.0000010.0000030.1) E-050.08) E-050.07) E-050.0000030.14) E-050.0000050.0000090.0000060.0000050.0000120.0000110.0000020.6) E-060.0000020.2) E-060.2) E-060.03) E-050.2) E-060.2) E-060.2) E-060.02) E-05

0.00070.000060.000004

0.04) E-050.0000020.0000020.09) E-06

0.00070.000100.00002

0.40.0010.00100.00010.00010.000021.5) E-050.0000150.000020.000010.000010.0000100.000020.00002

rel err

( 3.6 )( 2.8 )( 0.95)( 2.8 )( 1.2 )( 2.1 )( 1-6 )( 1-8 )( 1.5 )(10. )( 1-2 )( 0.93)( 0.53)( 1-3 )( 1-6 )( 2.7 )( 0.61)( 2.1 )( 0.9 )( 0.58)( 2.0 )( 1-9 )( 2.2 )( 0.75)( 1-6 )( 6 . 8 )( 0.84)( 4.4 )( 2.3 )( 2.0 )( 3.0 )( 2.1 )( 7.1 )( 1-7 )

( 1.6 )( 0.84)( 1-0 )

( 1-9 )( 2.0 )( 0.86)( 1-4 )

( 1-9 )( 3.9 )( 6.7 )

( 1-1 )( 5.0 )( 5.1 )(10. )( 2.4 )( 4.4 )(20. )( 8.7 )( 2.5 )( 6.7 )( 6.7 )( 2.0 )(10. )( 5.6 )

- 19 -

nuclide

95-Am-242m

95-Am-243

96-Cm-242

96-Cm-243

96-Cm-244

98-Cf-252

energy(keV)

48.6349.36766.89867.986.6892.5109.6111.1121.8135.17136.1152.75153.84163.24

74.6786.79

142.18

44.08101.93157.42561.02605.04

209.753228.184277.599285.460

42.82498.860

152.630

43.399100.2160.

+±±

±

+

±±±

++

±

+±±+±

+±±±

++

±

+

±

0.050.0040.020

0.03

0.06

0.060.060.04

0.150.150.15

0.030.040.050.100.10

0.0020.0020.0020.002

0.0080.0130.020

0.025

5.

emission(percent

99.5 *)0.190.0210.00730.040.0040.0240.0030.00600.0110.00960.00140.00460.024

68.20.3380.12

0.03250.00250.00140.000150.00011

3.2910.614.00.73

0.02480.00110.00099

0.01480.0130.0019


±±±±±±±±+±±±±

±+±

+±+±±

±++±

±+

+

0.010.0010.00020.010.0010.0010.0010.00020.0010.00030.00030.00010.001

1.40.0070.01

0.00120.00040.00020.000040.00003

0.100.30.40.02

0.00060.0001

0.0009

rel

( 5.( 4.( 2.(30.(30.( 4.(30.( 3.(10.( 3.(20.( 2.( 4.

( 2.( 2.( 8.

( 3.(20.(10.(30.(30.

( 3.( 2.( 2.( 2.

( 2.(10.

( 6.

err

3 )8 )7 )

))

2 ))

3 ))

1 ))

2 )2 )

1 )1 )3 )

7 )))))

0 )8 )9 )7 )

4 ))

1 )

*) Internal conversion not considered.

- 20 -

A-4: X-ray energies and intensities


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'

energy(keV)

72.87370.83282.57482.11583.09382.43484.86585.13485.44485.185

intensity

46.327 .610.70

5.59

+0.9±0.6±0.22±0.11

0.303±0.0120.045±0.0073.900.090.67

±0.08±0.04±0.07

per 100 K-shell vacancies (left column), orper 100 decays of nuclide given

83-Bi-212 a

0.127 +0.0210.075 ±0.012

0.0125±0.0021

- 21 -

elementtype

82-Pb

KKKKKKKKKKK

ala2fil133135Bl1

1321340P132 '

83-Bi

KKKKKKKKKKK

ala2131133135131'1321340P132 •

84-Po

KKKKKKKKKKK

ala2filB3fi5fil1

1321340P132'

86-Rn

KKKKKKKKKKK

ala2(31133135fil1

fi2B4OP02'

87-Fr

KKKKK

ala2BlB3135

energy(keV)

74.96972.80584.93884.45084.47084.78987.30087.58087.91188.00387.632

77.10774.81587.34986.83087.89287.19089.78490.07490.42190.52290.128

79.29076.86389.80789.25690.38889.63992.31792.61892.98393.09592.673

83.78781.06994.86892.24795.44994.96697.53097.85398.25798.38997.907

86.10583.23197.47496.81598.069

intensity

46.227.710.705.58

+0.910. 6+0.22+0.11

0.312±0.012

3.910.090.70

10.08+0.04+0.07

0.017±0.002

46.227.710.705.59

+0.910.6+0.21+0.11

0.321±0.013

3.930.090.73

+ 0.08+ 0.0410.08

0.031±0.003

46.127.710.705.57

10.9+0.6+0.21±0.11

0.33010.013

3.950.090.76

±0.0810.0410.08

0.049±0.005

46.027.910.605.56

10.910.610.21+0.11

0.34910.014

3.980.100.81

10.0810.0510.08

0.094+0.010

45.827.910.705.58

10.9+ 0.610.2110.11

0.358+0.014

per IOC K-shell vacancies (left column), orper 100 decays of nuclide given

81-T1-208 B-

32

1

0

82-

1710

6

1

83-

00

0

0

.6014

.27

367

10.1110.07

10.04

±0.013

-Pb-212 B-

705

27

86

±0.6±0.4

±0.22

±0.07

-Bi-212 B-

10060

035

Oil

±0.03±0.016

±0.010

±0.003

88-Ra-224 a

00

0.

0.

2012

072

023

±0.06±0.04

±0.020

±0.007

89-AC-224 a

0.0.

2817

±0.04±0.03

- 22 -

elementtype

87-Fr

KKKKK

1321340P132'

88-Ra

KKKKKKKKKKK

ala2131133135I 3 1 1

1321340P132'

8 9-Ac

KKKKKKKKKKK

ala2131133135131'132134OP132'

90-Th

KKKKKKKKKKK

91

KKKKKKKKKKK

ala2131133135131'

1321340P132'

L-Pa

ala2131133135131'

132134OP132'

energy(keV)

100.214100.548100.972101.118100.599

88.47185.431

100.13099.432100.73899.915

102.948103.295103.740103.899103.341

90.88687.675

102.841102.101103.462102.613105.738106.098106.563106.738106.137

93.35089.957105.604104.819106.239105.362108.582108.955109.442109.630108.990

95.86392.282

108.422107.595109.072108.166111.486111.870112.380112.575111.897

intensity

4.010.100.84

+0.08+0.05+0.09

0.114±0.012

45.728.010.705.59

±0.9+0. 6±0.21±0.11

0.362±0.015

4.040.110.86

±0.08±0.05±0.09

0.132±0.013

45.528.110.705.61

±0.910.610.2110.11

0.371±0.015

4.070.110.89

±0.08±0.05±0.09

0.146±0.015

45.428.110.705.61

±0.9±0.6±0.21±0.11

0.380±0.015

4.100.110.90

±0.08±0.05±0.09

0.160±0.016

45.328.110.705.64

±0.9±0.6±0.22±0.11

0.38910.016

4.130.120.93

±0.08±0.06±0.10

0.15610.016

per 100 K-shellper 100 decays

89-AC-224 a

0.032 ±0.005

89-AC-224 ec

35.22.

13.

4.1

±16.±10.

±6.

±1.9

91-Pa-231 a

0.780.476

0.280

0.092

±0.03±0.018

±0.011

±0.004

89-AC-228 13-

5.63.4

2.0

0.67

±1.3±0.8

±0.5

±0.15

90-Th-231 13-

0.630.39

0.228

0.076

±0.05±0.03

±0.019

±0.006

vacancies (leftof nuclide given

90-Th228 a

0.0288±0.00190.0175±0011

0.0103±0.0007

0.0034±0.0002

92-U-233 a

0.0169±0.00140.0104±0.0008

0.006110.0005

0.002010.0002

90-Th-233 13-

0.83 10.060.51 ±0.04

0.301 ±0.023

0.100 ±0.008

column), or

92-U-235 a

5.5 10.33.3610.21

1.9810.12

0.6610.04

93-Np-237 a

2.58±0.211.59±0.13

0.9410.08

0.3110.03

- 23 -

elementtype

92-U

KKKKKKKKKKK

ala2fil636561'6264OP132 '

92-U

KKKKKKKKKKK

ala213163135131'1321340P62'

93-Np

KKKKKKKKKKK

9'

KKKKKKKKKKK

ala261636561'62640P62'

1-Pu

ala261636561'62640P62'

94-Pu

KKKKK

ala2616365

energy(keV)

98.43494.654

111.298110.421111.964111.025114.445114.844115.377115.580114.866

98.43494.654

111.298110.421111.964111.025114.445114.844115.377115.580114.866

101.05997.069

114.224113.303114.912113.944117.463117.876118.429118.646117.891

103.73499.525

117.228116.244117.918116.930120.540120.969121.543121.768120.974

103.73499.525

117.228116.244117.918

45281050

4000

45281050

4000

45281050

4000

45281050

4000

45281050

intensity

.1

.2

.70

.65

10.9+ 0.6+ 0.22+ 0.11

.397±0.016

.15

.12

.97

+0.0810.0610.10

.15910.016

.1

.2

.70

.65

+ 0.910.610.2210.11

.39710.016

.15

.12

.97

10.0810.06+ 0.10

.15910.016

.1

.3

.70

.65

10.910.610.2210.11

.40510.016

.17

.12

.97

10.0810.0610.10

.16210.017

.1

.4

.70

.44

10.910.6+ 0.2210.11

.41310.016

.18

.13

.99

+0.08+0.0610.10

.15710.016

.1

.4

.70

.44

+0.9+0.610.22+0.11

.41310.016

per 100 K-shellper 100 <

91-Pa-232

1.76 101.10 10

0.644 10

0.217 10

93-Np-236

17.8 1111.6 10

6.5 +0

2.20 10

92-U-237

26. 1416. 13

9.6 11

3.3 10

93-Np-238

0.341 100.214 ±0

0.123 10

0.042610

96-Cm-243

23.0 1014.4 10

decays

13-

.07

.04

.024

.009

ec

.0

.6

.4

.13

13-

.5

.5

6-

.014

.009

.005

.0019

a

.6

.4

vacancies (leftof nuclide given

91-Pa-233 6-

1610

6

2

+32 ±1

0 11

0 +0

.6

.0

3

94-PU-239 a

(5(3

(2

(5

90106710

2510

5910

06)E-304)E-3

02)E-3

06)E-4

95-Am-241 a

(2(1

(7.

(2.

01 + 02610

4 +0

4910.

17)E-3ll)E-3

6 )E-4

22)E-4

93-Np-239 6-

23.15.

8.

2.

9 10.0 ±0.

6 10.

9810.

85

3

11

column) or

91-Pa-234 6-

2315

9

3

.3 11

.7 11

.2 +0

.11+0

.60

. 6

21

94-PU-241 a

(4(2

(1

(4

48108010

6 10

4610

09)E-407)E-4

l)E-4

12)E-5

95-Am-242 ec

5.3.

2.

0.

8 +1.6 10.

1 10.

72+0.

27

4

15

- 24 -

elementtype

94-Pu

K B2K 134K 0K PK B21

energy(keV)

120.540120.969121.543121.768120.974

4.0.0.0.

intensity

18 ±013 ±099 ±0157±0

080610016

per 100 K-shellper 100 decays

96-Cm-243 a

2.87 ±0.09

vacancies (left column), orof nuclide given

- 25 -

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.


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

Source of data:

[1] S.F Mughabghab, Neutron Cross Sections Vol. 1:Resonance Parameters andThermal Cross Sections, Part B: Z = 61-100; Academic Press, NY, 1984

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

nuclide

92-Th-232

92-U -238

94-PU-240

94-PU-242

averagedelayed

0.0531 ±

0.0439 ±

0.0095 ±

0.0221 ±

number ofneutrons

0.0023

0.0010

0.0008

0.0026

[3]

[3]

[3]

[3]

- 29 -

A-7: Prompt neutron multiplicity distributions P(v)

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) .

Table 7.1: P(v) values for thermal neutron induced fission (with uncertainties)

0

1

2

3

4

5

6

7

U-233

0.0262

0.1550

0.3328

0.3225

0.1325

0.0272

0.0037

0.0001

± 0.0012

± 0.0022

+ 0.0038

± 0.0020

± 0.0057

± 0.0024

± 0.0018

± 0.0001

0.0317

0.1720

0.3363

0.3038

0.1268

0.0266

0.0026

0.0002

U-235

± 0.0015

± 0.0014

± 0.0031

± 0.0004

± 0.0036

± 0.0026

± 0.0009

± 0.0001

Pu-239

0.0109

0.0995

0.2750

0.3270

0.2045

0.0728

0.0097

0.0006

± 0.0001

± 0.0028

± 0.0003

± 0.0041

± 0.0087

+ 0.0133

± 0.0027

± 0.0009

Pvi-241

0.0108

0.0895

0.2660

0.3313

0.2140

0.0749

0.0112

0.0023

± 0.0005

± 0.0014

± 0.0017

± 0.0041

± 0.0039

± 0.0050

± 0.0024

± 0.0013

Source of data:

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.


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


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


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


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.

Table B-2:

nuclide

36-Kr-85

40-Zr-95

41-Nb-95m

41-Nb-95

44-RU-103

45-Rh-106

51-Sb-125

energy(ke

513.997

235.680724.1990756.729

235.680

765.807

53.2770294.980443.777497.054557.022610.330

511.8640616.22621.93873.49

1050.3601128.0421562.2191766.251796.9311927.221988.5952112.5992366.042405.96

35.4910172.626176.316

>V)

1

++±

1

1

++111±

+++11+11++++1±

111

0.005

0.0200.00500.012

0.020

0.006

0.00870.0190.0120.0100.0140.02

0.00310.090.060.050.0480.0210.0480.050.0540.090.0930.0880.070.09

0.00050.0210.010

emission probability(percent per

0.434 1

0.294 +44.17 154.46 1

24.9 +

99.81 1

0.443 ±0.303 10.345 1

91.0 10.868 1 (5.76 1

20.4 10.738 +9.93 10.439 11.56 10.404 10.163 10.0342710.0277410.0153 10.0261110.0340 10.0232610.0140 1

4.29 10.1820 16.79 1

0.010

0.0160.130.10

0.8

0.03

0.0110.0060.0051.3).O120.07

0.40.0310.230.0110.050.010.0040.00130.00110.00060.00110.00200.00120.0008

0.180.00400.15

decay)

( 2.3 )

( 5.5 )( 0.36)( 0.18)

( 3.2 )

( 0.03)

( 2.5 )( 2.0 )( 1.5 )( 1.4 )( 1.4 )( 1.2 )

( 2.0 )( 4.2 )( 2.3 )( 2.5 )( 3.2 )( 2.5 )( 2.5 )( 3.8 )( 4.0 )( 3.9 )( 4.2 )( 5.9 )( 5.2 )( 6.4 )

( 4.2 )( 2.2 )( 2.2 )

syst.err.

2

0

0

0

1

2

1

27

18

6

03

12

9

00

- 36 -

nuclide

51-Sb-125

53-1 -131

54-Xe-131m

54-Xe-133

55-CS-134

55-CS-137

56-Ba-140

57-La-140

58-Ce-141

energy(Ice

380.452427.875463.365600.600606.718635.954671.445

80.185284.305364.489636.989642.719722.911

163.9310

80.997

475.365563.246569.331604.721795.864801.9531038.6101167.9681365.185

661.6600

29.966132.687162.660304.849423.722437.575537.261

109.4070131.1130173.5290241.9540266.5490328.7570397.6620432.493487.026751.637815.783867.846919.550925.189950.991596.212347.882521.402547.342899.613118.51

145.4400

V)

+±±±±±±

±±±+±±

±

±

+

±±±±±+±±

±

++±±±±

±

+±±±±+±±±±+±±±+±±+±±

0.0080.0060.0040.0040.0030.0050.004

0.0020.0050.0050.0040.0050.005

0.0068

0.003

0.0020.0050.0030.0020.0040.0040.0070.0050.014

0.0030

0.0010.0010.0010.0030.0010.0020.009

0.00640.00720.00850.00810.00800.00890.00900.0120.0180.0180.0200.0200.0230.0200.030.040.050.050.110.16

± 0.16

± 0.0028


1.52029.4410.4517.785.0211.321.800

2.626.14

81.77.170.21901.77

1.960

38.0

1.4868.35

15.3897.6285.538.690.9881.7893.014

85.1

14.10.2026.224.293.151.929

24.39

0.2190.4670.1270.4140.466

20.30.0732.9045.54.33

23.285.502.666.900.51995.4000.8493.460.10300.06500.0250

48.2

+±±+±±±

+

±±+±±

±

±

+

±++++++±

±

+++±±±±

+

±±±±++±±+±+±+++±±++±

±

0.0340.660.230.400.110.250.044

0.040.070.80.100.00490.03

0.059

0.7

0.0100.040.060.030.040.040.0040.0070.012

0.2

0.50.0050.080.050.040.010.08

0.0040.0100.0040.0080.0080.30.0050.030.60.040.20.070.030.070.0070.0760.0170.040.00280.00190.0009

0.3

decay)

( 2.2 )( 2.2 )( 2.2 )( 2.2 )( 2.2 )( 2.2 )( 2.4 )

( 1-5 )( 1.1 )( 1.0 )( 1-4 )( 2.2 )( 1-7 )

( 3.0 )

( 1-8 )

( 0.7 )( 0.5 )( 0.4 )( 0.03)( 0.05)( 0.5 )( 0.4 )( 0.4 )( 0.4 )

( 0.24)

( 3.5 )( 2.5 )( 1-3 )( 1-2 )( 1.3 )( 0.5 )( 0.3 )

( 1-8 )( 2.1 )( 3.1 )( 1.9 )( 1-7 )( 1.5 )( 6.8 )( 1.0 )( 1-3 )( 0.9 )( 0.9 )( 1-3 )( 1-1 )( 1.0 )( 1-3 )( 0.08)( 2.0 )( 1.2 )( 2.7 )( 2.9 )( 3.5 )

( 0.6 )

syst.err.

0.99

3.0

2.7

1.00

0.24

0.90

0.08

0.80

- 37 -

nuclide

58-Ce-144

59-Pr-144

60-Nd-147

61-Pm-147

61-Pm-148m

61-Pm-148

63-EU-154

energy(keV)

80.120133.5150

696.5101489.1602185.662

91.105275.385319.414398.155439.910531.013

121.258

75.7098.479189.645288.124311.634414.071432.763501.279550.274599.757611.270629.962725.704915.3481013.827

550.274611.270914.8501465.120

123.071188.252247.9670401.258444.490478.292557.627582.061591.762625.254676.600692.425715.828723.305756.804815.585845.417850.687873.19892.781904.076996.262

1004.7251047.3701118.2931128.5601140.711

+

±

+

±±

±±±±±±

±

+

±±±±+++±±±±+±

±

+

±±±

+

±+

±±++±±±±±±±±±±±±±+±±±+±±

0.0050.002

0.0030.0050.007

0.0020.0130.0130.0160.0160.016

0.043

0.100.0170.0160.0160.0150.0130.0170.0160.0150.0160.0150.0160.0140.0150.015

0.0150.0150.0160.018

0.0010.0080.00740.0140.0060.0410.0260.0270.0050.0070.0120.0040.0220.0050.0050.0170.0290.0290.0050.0090.0060.0060.0070.0340.0430.0080.009


1.3611.09

1.3420.2780.694

27.90.8011.950.8711.20

13.09

0.0020

1.02102.4731.09112.513.9018.595.336.72

94.512.495.4688.6332.717.1020.20

22.001.021

11.4622.20

40.60.2396.910.2090.5620.2170.2680.8894.960.3180.1571.7920.188

20.114.540.5130.5880.24212.200.5150.89310.5317.910.1340.10300.3180.216

±±

+

±±

±±±±±

±

+

±±±±+++±±±±±±±

±±+

±

+++±±+±±±+++±+±++±±++±+±++±

0.060.20

0.0140.0050.016

1.10.0590.140.0650.100.89

0.0001

0.00760.0660.0260.130.060.210.080.091.00.150.120.660.40.220.23

0.660.0310.340.50

0.40.0050.050.0140.0060.0140.0030.0090.040.0040.0070.0150.0090.150.040.0050.0050.0040.080.0050.0070.070.120.0150.00670.0040.014

decay)

( 4.4( 1.8

( 1.0( 1.8( 2.3

( 3.9( 7.4( 6.9( 7.5( 8.0( 6.8

( 3.9

( 0.75( 2.7( 2.4( 1.0( 1.5( 1.1( 1.5( 1.3( 1.0( 1.2( 2.1( 0.75( 1.2( 1.3( 1.1

( 3.0( 3.0( 3.0( 2.3

( 1.0( 2.1( 0.7( 6.6( 1.0( 6.5( 1.1( 1.0( 0.8( 1.2( 4.5{ 0.8( 4.8 )( 0.7 )( 0.9 )( 1.0 )( 0.9 )( 1.6 )( 0.7 )( 1-0 )( 0.8 )( 0.7 )( 0.7 )(10. )( 6.5 )( 1-3 )( 6.4 )

syst.err.

1

1

3

3

0

2.

5.

44

04

9

9

75

25

6

- 38 -

n u d i d e

63-EU-154

63-EU-155

energy( k e

1241.3931246.1501274.4361494.0481596.495

45.297260.008686.066086.5420

105.3120

V)

±±±±±+

±±±

0.0430.0090.0060.0090.018

0.00130.00100.00470.00200.0020

emission p r o b a b i l i t y(percent pe r

0.1330.864

35.00.7001.788

1.331.130.150

30.721.2

±±±+

±+

±±±±

0.0050.0070 . 30.0080.015

0.030.050.0160 . 70 . 5

decay)

( 3.6 )( 0.8 )( 0.8 )( 1.1 )( 0.8 )

( 2 .3 )( 4.4 )(10.7 )( 2 .3 )( 2 .4 )

s y s t .err.

6 . 5

- 39 -

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.


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

[2] S.F. Mughabghab et al., Neutron Cross Sections Vol. 1: Resonance Parametersand Thermal Cross Sections, Part A: Z=l-60; Academic Press, NY, 1981

[3] S.F. Mughabghab, Neutron Cross Sections Vol. 1: Resonance Parameters andThermal Cross Sections, Part B: Z=61-100; Academic Press, NY, 1984

- 40 -

[4] F. De Corte et al., J. Radioanal.Nucl.Chem. 133(1989)53

[5] JEF-2.2: the Joint European File, NEADB, Paris

[6] JENDL-3.2: the Japanese Evaluated Nuclear Data Library

[7] ENDF/B-6: the US Evaluated Nuclear Data File, version 6

The evaluated data files of complete o(E) data, ENDF/B-6 and JENDL-3.2 areavailable from the 4 Data Centres (see Introduction) upon request.

Table B-3:

Nuclide

36-Kr-828384

8586

40-Zr-90919293949596

42-MO-95969798100

44-Ru-lOO101102103104106

54-Xe-130

131132

133g

136

55-CS-133

134g135137g

58-Ce-144g

Thermal

oaa(m)o(g)a(m+g)oo

oaaooa.o

oaao.a

a.o.a.aa.o

o. (m)o.(g)a. (m+g)o.o. (m)o. (m+g)oro. (m)a. (m+g)o.o.

a. (m)a. (m+g)oraOp(g)

a

neutron cross section(b)

30.0180.00.0900.0420.1101.660.003

0.0111.240.222.6

+++±1±

±1+±

0.049910.490.0229+

14.00.52.10.1300.199

5.03.41.217.710.320.146

0.456.06.45

85.00.0500.450

190.00.0030.265(2.650.26

2.529.0140.0

8.70.110

1.0

+

1+±±

+1±

±±

+

±±±+i11±+±

±±+±

±

10.030.00.0130.0040.0150.20.002

0.0050.250.061.40.0024

0.0010

0.50.20.50.0060.003

0.60.90.07

0.020.045

0.101.01.0

10.00.0100.06090.00.00030.0200.11) E+060.02

0.21.5

12.00.50.033

0.1

Resonance

cc

c

c

c

ccc

c

<b

190.0183.02.40.83.21.80.1

0.146.80.63

20.00.306.55.3

109.024.014.06.93.75

11.088.04.260.04.31.8

1.1713.7214.89

900.00.94.6

1340.10.3

7600.00.74

30.0422.0106.066.00.35

2.6

Integral)

±±

++

±

1+±1±±

++++±

+++

20.025.0

0.51.00.04

1.30.11

10.00.071.40.3

5.04.03.00.30.15

0.717.00.1

1 20.0+

±

+±+

±+

1±

+±

±

0.10.4

100.00.20.6

500.0.21

6.023.0

8.00.07

0.3

Ref.

[1][2][1][1][1][1,2][1]

[2][1][1][1][1][1][5]

[2][1][2][5][2]

[1][1][2][1][2][1]

[1][1][1][2][1,2][1,2]

[1][1][2][1,2]

[1][1][6][1][6]

[1,2]

- 41 -

Nuclide

59-Pr-141143

60-Nd-142143144g145146147148150

61-Pm-147

148m148g149151

62-Sm-147148149150151152153154

63-EU-151

152153154g155

Thermal

o. (m)o. (m+g)o

oa.aa.a.ao.a.

aim)o(g)a(m+g)aOr

oa

aoao.oo.a.o.

a(m2)o(ml)o(g)o(total)oo.o.oro

neutron(b)

3.911.590.0

18.7325.0

3.642.01.4

440.02.51.2

85.096.0

181.022000.02000.01400.0173.0

64.02.7

41000.0102.0

15000.0206.0420.0

7.74

4.23211.05935.09146.0

12800.0312.01500.04040.03950.0

cross section

± 0.3± 0.3± 10.0

± 0.7± 10.0± 0.3± 2.0± 0.1+ 150.0± 0.2± 0.2

± 5.0± 2.0± 7.0±2500.0±1000.0± 300.0

± 5.0± 0.6±2000.0± 5.0±1800.0± 6.0± 180.0 3)± 0.46 4)

± 2.0± 82.0± 73.0± 109.0± 600.± 7.0 5)± 400.0+ 125.0 6)± 125.0 6)

Resonance Integral(b)

17.8190.0

8.5136.05.0

255.02.7

540.014.014.5

910.01320.02230.03600.02510.0825.0

1400.0

650.027.0

3700.0358.0

3100.02960.03700.0

33.3

1823.03552.05367.02170.01420.01500.01680.0

C 23200.0

± 3.5± 25.0

± 1.0± 35.0± 1.0± 40.0± 0.4± 150.0± 1.5± 2.0

± 265.0± 85.0± 70.0±2400.0

± 50.0± 400.0

± 50.0± 14.0+ 400.0± 50.± 500.0± 150.0±2000.0± 3.0

± 146.0± 264.0± 263.0

± 100.0± 450.0± 300.0± 300.0

Ref.

[1][2]

[1][1]fl][1][1][1][1,2][1,2]

[1] l)[1][1] 2)11/3][6][1][1]

[1][1,3][1][3][1][1][1][4] «)

[1][1][1][6][3] 5)[1][1][3] 6)

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.


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


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


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.


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

e-mail: [email protected]: (43-1)20607

cable: INATOM VIENNA atelex: 1-12645 atom a

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

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