Beta Decay and Decay Heat: Beta Decay and Decay Heat: Problem of Identifying Problem of Identifying

Problem Fission ProductsProblem Fission Products

A L NicholsA L Nichols

Nuclear Data SectionNuclear Data SectionInternational Atomic Energy AgencyInternational Atomic Energy Agency

Vienna, AustriaVienna, Austria

12-14 December 200512-14 December 2005

Decay Heat: Points of NoteDecay Heat: Points of Note

• Fission productsFission productsfission yieldsfission yieldsdecay datadecay datacross sectionscross sections

• Actinides – maximum of ~ 20-30% of Actinides – maximum of ~ 20-30% of total decay heat leading up to ~ 10total decay heat leading up to ~ 1088 s s

• Activation products – extremely minor Activation products – extremely minor contribution to thermal systemscontribution to thermal systems

1990s: Inadequate and Discrepant 1990s: Inadequate and Discrepant Decay Data in Decay Heat Decay Data in Decay Heat CalculationsCalculations

• FrFrééddééric Joliot – Otto Hahn Summer ric Joliot – Otto Hahn Summer School, Cadarache, France, 2000School, Cadarache, France, 2000

• also presented at Workshop on “Nuclear also presented at Workshop on “Nuclear Reaction Data and Nuclear Reactors: Reaction Data and Nuclear Reactors: Physics, Design and Safety”, The Abdus Physics, Design and Safety”, The Abdus Salam ICTP, Trieste, Italy, 25 February – Salam ICTP, Trieste, Italy, 25 February – 28 March 2002; ICTP Lecture Notes 20, 28 March 2002; ICTP Lecture Notes 20, Editors – M. Herman, N. Paver, 2005Editors – M. Herman, N. Paver, 2005

1990s: Inadequate and Discrepant 1990s: Inadequate and Discrepant Decay Data in Decay Heat Decay Data in Decay Heat CalculationsCalculations• Consultation and debate within Consultation and debate within

Europe - Europe - 27 FPs27 FPs – various – various applications, but also for decay heat applications, but also for decay heat calculationscalculations

• Theoretical data for Theoretical data for 3535 neutron-rich neutron-rich nuclides – short cooling timesnuclides – short cooling times

Evaluation of discrete decay data - consistency of data sets requested forJEFF-3.

Radionuclide Consistency(% Deviation)

Radionuclide Consistency(% Deviation)

33-As-85

34-Se-79

(34-Se-79m)

35-Br-87

35-Br-88

35-Br-89

35-Br-90

35-Br-91

37-Rb-93

37-Rb-94

37-Rb-95

(39-Y-98)

39-Y-98m

39-Y-99

40-Zr-93

(41-Nb-93m)

45-Rh-106

(45-Rh-106m)

50-Sn-126

0.0988*

0.0000

-0.0962

-0.1976*

0.2554*

0.0534*

0.1331*

0.0274*

-0.0182*

-0.0527*

-0.2394*

-0.0432*

-0.2944*

-0.0741*

1.2384

-0.3678

-0.0243

-0.0487

0.0293

(51-Sb-126)

(51-Sb-126m)

(51-Sb-126n)

51-Sb-127

51-Sb-135

(52-Te-127)

(52-Te-127m)

52-Te-132

53-I-132

(53-I-132m)

53-I-137

53-I-138

53-I-139

57-La-140

59-Pr-143

59-Pr-144

(59-Pr-144m)

62-Sm-147

65-Tb-161

-0.0653

-0.1714

-0.3560

-0.0431

-0.0198*

-0.0037

-0.0908

0.1077

-0.0832

-0.3723

0.1276*

-0.1955*

-0.0552*

-0.0108

0.0000

0.0382

-0.0860

-0.0023

-0.0324

Additional short-lived daughter and related metastable/ground state radionuclides are inparentheses, and were also evaluated.*Beta-decay mode only.

Short-lived fission products requested for JEFF-3 - US ENDF/B-VI decay data adopted ormodified unless stated otherwise.

Radionuclide Half-life (sec) ‡Continuum Spectra - Energy Range (keV)*

Gamma Beta Neutron39-Y-104 0.13(2) 0(500) - 12730 0 - 12690 0 - 551039-Y-105 0.15(2) 0(500) - 10820 0 - 10790 0 - 684040-Zr-105 0.6(2) 0(500) - 8290 0 - 8260 0 - 2260

40-Zr-106 0.9(2) 0(500) - 6380 0 - 6350 0 - 257040-Zr-107 0.24(4) 0(500) - 9230 0 - 9200 0 - 395041-Nb-109 0.19(6) 0(500) - 8760 0 - 8730 0 - 530042-Mo-109 0.5(2) 0(500) - 6700 0 - 6670 0 - 1200

42-Mo-111 0.5(2) 0(500) - 8020 0 - 7990 0 - 221042-Mo-112 1.0(2) 0(500) - 6020 0 - 5990 0 - 272043-Tc-113 0.13(4) 0(500) - 7540 0 - 7510 0 - 408043-Tc-114 0 20(4) 0(500) - 10610 0 - 10580 0 - 479043-Tc-115 0.27(5) 0(500) - 8870 0 - 8840 0 - 591043-Tc-116 0.12(2) 0(500) - 11860 0 - 11830 0 - 665044-Ru-115 0.7(2) 0(500) - 7250 0 - 7220 0 - 140044-Ru-116 1.7(3) 0(500) - 5510 0 - 5480 0 - 215044-Ru-117 0.34(7) 0(500) -8500 0 - 8470 0 - 318044-Ru-118 0.7(2) 0(500) - 6530 0 - 6500 0 - 368044-Ru-119 0.19(4) 0(500) - 9290 0 - 9260 0 - 444045-Rh-118 0.32(6) 0(500) - 9970 0 - 9940 0 - 341045-Rh-120 0.17(3) 0(500) - 10770 0 - 10730 0 - 483045-Rh-121 0.25(5) 0(500) - 8790 0 - 8760 0 - 599046-Pd-121 0.6(1) 0(500) - 7560 0 - 7530 0 - 152051-Sb-141 0.3(1) No entry in US ENDF/B-VI; other theoretical data adopted

57-La-152 0.28(6) 0(500) - 8810 0 - 8770 0 - 398058-Ce-153 1.5(3) 0(500) - 5820 0 - 5790 0 - 162058-Ce-154 2.0(4) 0(500) - 5010 0 - 4970 0 - 164058-Ce-158 1.0(2) No entry in US ENDF/B-VI; other theoretical data adopted

59-Pr-156 0.5(1) 0(500) - 8690 0 - 8660 0 - 279059-Pr-157 0.30(6) 0(500) - 8130 0 - 8100 0 - 359060-Nd-157 2.5(5) 0(500) - 5560 0 - 5520 None60-Nd-158 0.7(2) 0(500) - 5000 0 - 4970 0 - 32060-Nd-159 0.5(1) 0(500) - 7150 0 - 7120 0 - 123060-Nd-160 0.30(6) 0(500) - 6350 0 - 6320 0 - 183061-Pm-159 3.0(6) 0(500) - 5650 0 - 5620 0 - 41061-Pm-160 2.0(4) 0(500) - 7800 0 - 7770 0 - 1130

‡ Adopted from a combination of Audi et al (1997), Takahashi et al (1973) and US ENDF/B-VI(Dunford, 1992); uncertainties are given in parentheses (for example, 0.13(2) means 0.13 ± 0.02).

* Expressed in terms of incremental units of 10 keV starting from zero (first incremental energy stepof continuum gamma spectra is from zero to 500 keV, as noted in parentheses).

Neutron spectrum adjusted to 0-1794 keV. Neutron spectrum adjusted to 0-620 keV.

FISPIN10 Decay Heat FISPIN10 Decay Heat CalculationsCalculationsRobert Mills: Nexia Solutions, Sellafield, UKRobert Mills: Nexia Solutions, Sellafield, UK

• JEFF-3.1 decay data files, and JEFF-3.1 fission yield filesJEFF-3.1 decay data files, and JEFF-3.1 fission yield files

• FISPIN10 – used to calculate FP number densities following FISPIN10 – used to calculate FP number densities following a single fissiona single fission

• decaying FPs from 0.1 to 10decaying FPs from 0.1 to 10+9+9 secs after fuel irradiation secs after fuel irradiation• ordered in terms of those that contribute the most ordered in terms of those that contribute the most

uncertainty to the overall uncertainty of the calculated uncertainty to the overall uncertainty of the calculated decay heatdecay heat

BUT these data still require further detailed assessmentBUT these data still require further detailed assessment

FISPIN10 Decay Heat FISPIN10 Decay Heat CalculationsCalculations

• 235235UUthth

• 239239PuPuthth

• 238238UUff

• 232232ThThff

FPs FPs 0.5% of the resulting decay heat as a 0.5% of the resulting decay heat as a function of cooling time after irradiationfunction of cooling time after irradiation

235235UUthth: : Dominant Uncertainties in Dominant Uncertainties in

JEFF-3.1JEFF-3.1

• Short cooling times – uncertainties in FYsShort cooling times – uncertainties in FYs

• Half-lives:Half-lives:9898YYm m (( 10%), 10%), 100100Nb (Nb ( 13%), 13%), 102102Nb (Nb ( 15%) 15%)

• Energy release: Energy release: 8787Br (Br ( 17%), 17%), 8989Sr (Sr ( 40%), 40%), 9797Sr (Sr (no uncertaintyno uncertainty), ), 101101Nb (Nb ( 15%), 15%), 102102Nb (Nb (no uncertaintyno uncertainty), ), 143143La (La ( 53%) 53%)

239239PuPuthth : 1.0 s : 1.0 sNuclide Nuclide Energy release rate eV per second per fission Energy release rate eV per second per fission Ebeta Ebeta Egamma Egamma Ealpha Ealpha

41-NB-103 41-NB-103 2.3526E+04 2.3526E+04 2.3526E+04 2.3526E+04 0.0000E+00 0.0000E+00 6%6% 41-NB-104M 41-NB-104M 1.2554E+04 1.2554E+04 1.2554E+04 1.2554E+04 4.4028E-01 4.4028E-01 3%3%39-Y-98M39-Y-98M 1.4565E+04 1.4565E+04 1.7209E+04 1.7209E+04 8.2312E+01 8.2312E+01 4%4% 41-NB-10241-NB-102 1.6423E+04 1.6423E+04 1.6423E+04 1.6423E+04 0.0000E+00 0.0000E+00 4%4% 39-Y-9939-Y-99 2.0826E+04 2.0826E+04 6.4749E+03 6.4749E+03 5.1960E+01 5.1960E+01 3.2%3.2%38-SR-9738-SR-97 1.1495E+04 1.1495E+04 1.1495E+04 1.1495E+04 5.3695E-01 5.3695E-01 2.7%2.7%43-TC-109 43-TC-109 8.4527E+03 8.4527E+03 8.4527E+03 8.4527E+03 8.5152E-01 8.5152E-01 2%2%55-CS-143 55-CS-143 9.7006E+03 9.7006E+03 9.7006E+03 9.7006E+03 4.0121E+01 4.0121E+01 54-XE-141 54-XE-141 8.3732E+03 8.3732E+03 8.3732E+03 8.3732E+03 2.9217E-01 2.9217E-01 39-Y-98 39-Y-98 1.1206E+04 1.1206E+04 1.0535E+04 1.0535E+04 4.1903E+00 4.1903E+00 55-CS-142 55-CS-142 2.2756E+04 2.2756E+04 5.3016E+03 5.3016E+03 0.0000E+00 0.0000E+00 40-ZR-101 40-ZR-101 1.9095E+04 1.9095E+04 4.8905E+03 4.8905E+03 0.0000E+00 0.0000E+00 42-MO-107 42-MO-107 6.4492E+03 6.4492E+03 6.4492E+03 6.4492E+03 0.0000E+00 0.0000E+00 40-ZR-103 40-ZR-103 5.9344E+03 5.9344E+03 5.9344E+03 5.9344E+03 0.0000E+00 0.0000E+00 39-Y-100 39-Y-100 4.6434E+03 4.6434E+03 4.6434E+03 4.6434E+03 8.3444E+00 8.3444E+00 38-SR-96 38-SR-96 1.8752E+04 1.8752E+04 8.7943E+03 8.7943E+03 0.0000E+00 0.0000E+00 39-Y-100M 39-Y-100M 4.3689E+03 4.3689E+03 4.3689E+03 4.3689E+03 0.0000E+00 0.0000E+00 41-NB-105 41-NB-105 5.0734E+03 5.0734E+03 5.0734E+03 5.0734E+03 1.4243E+011.4243E+01

239239PuPuthth : 1.0 s : 1.0 sNuclide Nuclide Energy release rate eV per second per fission Energy release rate eV per second per fission Ebeta Ebeta EgammaEgamma Ealpha Ealpha 37-RB-9437-RB-94 6.6126E+03 6.6126E+03 5.8577E+03 5.8577E+03 2.1434E+01 2.1434E+01 1.5%1.5%40-ZR-102 40-ZR-102 9.8858E+03 9.8858E+03 1.1729E+03 1.1729E+03 0.0000E+00 0.0000E+00 37-RB-9537-RB-95 4.3081E+03 4.3081E+03 4.0236E+03 4.0236E+03 1.1949E+01 1.1949E+01 1.0%1.0% 39-Y-97M 39-Y-97M 1.8186E+04 1.8186E+04 1.8221E+04 1.8221E+04 2.6623E+00 2.6623E+00 53-I-13853-I-138 5.6520E+03 5.6520E+03 2.7526E+03 2.7526E+03 1.0986E+01 1.0986E+01 1.0%1.0% 41-NB-104 41-NB-104 4.5696E+03 4.5696E+03 4.5696E+03 4.5696E+03 1.4174E-01 1.4174E-01 38-SR-98 38-SR-98 4.6675E+03 4.6675E+03 1.1405E+03 1.1405E+03 0.0000E+00 0.0000E+00 43-TC-108 43-TC-108 8.0213E+03 8.0213E+03 8.0213E+03 8.0213E+03 0.0000E+00 0.0000E+00 53-I-13953-I-139 4.6636E+03 4.6636E+03 1.2379E+03 1.2379E+03 2.0467E+01 2.0467E+01 0.7%0.7%52-TE-137 52-TE-137 2.7786E+03 2.7786E+03 2.7786E+03 2.7786E+03 1.4208E+01 1.4208E+01 54-XE-142 54-XE-142 2.7648E+03 2.7648E+03 2.7648E+03 2.7648E+03 1.3767E+00 1.3767E+00 57-LA-148 57-LA-148 4.0528E+03 4.0528E+03 2.2550E+03 2.2550E+03 0.0000E+00 0.0000E+00 56-BA-145 56-BA-145 4.9528E+03 4.9528E+03 4.9528E+03 4.9528E+03 0.0000E+00 0.0000E+00 41-NB-106 41-NB-106 2.5104E+03 2.5104E+03 2.5104E+03 2.5104E+03 2.0842E+01 2.0842E+01 42-MO-108 42-MO-108 2.5479E+03 2.5479E+03 2.5479E+03 2.5479E+03 0.0000E+00 0.0000E+00 56-BA-146 56-BA-146 2.9970E+03 2.9970E+03 2.9970E+03 2.9970E+03 0.0000E+00 0.0000E+00 51-SB-134 51-SB-134 4.7464E+03 4.7464E+03 8.1988E+01 8.1988E+01 0.0000E+00 0.0000E+00 55-CS-144 55-CS-144 3.2015E+03 3.2015E+03 3.2015E+03 3.2015E+03 2.4051E+012.4051E+01

239239PuPuthth : 1.0 s : 1.0 sNuclide Nuclide Energy release rate eV per second per fission Energy release rate eV per second per fission Ebeta Ebeta Egamma Egamma Ealpha Ealpha

36-KR-92 36-KR-92 3.9726E+03 3.9726E+03 2.7613E+03 2.7613E+03 0.0000E+00 0.0000E+00 41-NB-102M 41-NB-102M 4.5521E+03 4.5521E+03 4.1878E+03 4.1878E+03 0.0000E+00 0.0000E+00 40-ZR-99 40-ZR-99 1.4095E+04 1.4095E+04 7.7061E+03 7.7061E+03 0.0000E+00 0.0000E+00 39-Y-97 39-Y-97 5.1214E+03 5.1214E+03 4.3350E+03 4.3350E+03 0.0000E+000.0000E+0041-NB-100M 41-NB-100M 2.3203E+03 2.3203E+03 2.3397E+03 2.3397E+03 0.0000E+00 0.0000E+00 41-NB-10041-NB-100 4.8561E+03 4.8561E+03 1.3795E+03 1.3795E+03 0.0000E+00 0.0000E+00 0.74%0.74%37-RB-93 37-RB-93 3.9740E+03 3.9740E+03 4.8836E+03 4.8836E+03 7.7866E+00 7.7866E+00 1.0%1.0% 40-ZR-100 40-ZR-100 5.3875E+03 5.3875E+03 9.9503E+02 9.9503E+02 0.0000E+00 0.0000E+00 41-NB-10141-NB-101 4.8424E+03 4.8424E+03 6.3558E+02 6.3558E+02 0.0000E+00 0.0000E+00 0.65%0.65%54-XE-140 54-XE-140 2.4783E+03 2.4783E+03 2.4783E+03 2.4783E+03 0.0000E+00 0.0000E+00 57-LA-147 57-LA-147 4.4842E+03 4.4842E+03 4.0022E+02 4.0022E+02 0.0000E+00 0.0000E+00 42-MO-106 42-MO-106 3.5687E+03 3.5687E+03 3.5687E+03 3.5687E+03 0.0000E+00 0.0000E+00 52-TE-135 52-TE-135 3.6719E+03 3.6719E+03 5.7800E+02 5.7800E+02 0.0000E+00 0.0000E+00 37-RB-92 37-RB-92 5.3473E+03 5.3473E+03 3.2544E+03 3.2544E+03 0.0000E+00 0.0000E+00 39-Y-96 39-Y-96 6.8169E+03 6.8169E+03 1.7036E+02 1.7036E+02 0.0000E+00 0.0000E+00 ---------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------- Totals Totals 4.8955E+05 4.8955E+05 3.5208E+05 3.5208E+05 7.5696E+02 7.5696E+02

80.50% of all nuclides80.50% of all nuclides

239239PuPuthth : 1 min : 1 minNuclide Nuclide Energy release rate eV per second per fission Energy release rate eV per second per fission Ebeta Ebeta Egamma Egamma EalphaEalpha

53-I-13753-I-137 4.3704E+02 4.3704E+02 2.8630E+02 2.8630E+02 9.2438E+00 9.2438E+00 3.2%3.2%53-I-136 53-I-136 3.5992E+02 3.5992E+02 4.2571E+02 4.2571E+02 0.0000E+00 0.0000E+00 41-NB-98 41-NB-98 6.2536E+02 6.2536E+02 1.0327E+02 1.0327E+02 0.0000E+00 0.0000E+00 52-TE-135 52-TE-135 4.4471E+02 4.4471E+02 7.0002E+01 7.0002E+01 0.0000E+00 0.0000E+00 53-I-136M 53-I-136M 3.6907E+02 3.6907E+02 3.6907E+02 3.6907E+02 0.0000E+00 0.0000E+00 52-TE-136 52-TE-136 1.1528E+02 1.1528E+02 1.7469E+02 1.7469E+02 0.0000E+00 0.0000E+00 51-SB-133 51-SB-133 7.6329E+01 7.6329E+01 2.5365E+02 2.5365E+02 0.0000E+00 0.0000E+00 44-RU-109 44-RU-109 1.7440E+02 1.7440E+02 2.7795E+02 2.7795E+02 0.0000E+00 0.0000E+00 43-TC-107 43-TC-107 5.0802E+02 5.0802E+02 1.2722E+02 1.2722E+02 0.0000E+00 0.0000E+00 42-MO-105 42-MO-105 6.8414E+02 6.8414E+02 1.9630E+02 1.9630E+02 0.0000E+00 0.0000E+00 43-TC-106 43-TC-106 8.3182E+02 8.3182E+02 9.3787E+02 9.3787E+02 0.0000E+00 0.0000E+00 54-XE-139 54-XE-139 5.1348E+02 5.1348E+02 5.1348E+02 5.1348E+02 0.0000E+00 0.0000E+00 42-MO-103 42-MO-103 4.8207E+02 4.8207E+02 2.3300E+02 2.3300E+02 0.0000E+00 0.0000E+00 45-RH-110 45-RH-110 1.9344E+02 1.9344E+02 4.1786E+02 4.1786E+02 0.0000E+00 0.0000E+00 57-LA-145 57-LA-145 2.7171E+02 2.7171E+02 1.1307E+02 1.1307E+02 0.0000E+00 0.0000E+00 55-CS-140 55-CS-140 6.8755E+02 6.8755E+02 5.8667E+02 5.8667E+02 0.0000E+00 0.0000E+00 50-SN-131M 50-SN-131M 8.2947E+01 8.2947E+01 8.2947E+01 8.2947E+01 0.0000E+00 0.0000E+00 54-XE-140 54-XE-140 1.2500E+02 1.2500E+02 1.2500E+02 1.2500E+02 0.0000E+00 0.0000E+00

239239PuPuthth : 1 min : 1 minNuclide Nuclide Energy release rate eV per second per fission Energy release rate eV per second per fission Ebeta Ebeta Egamma Egamma EalphaEalpha55-CS-141 55-CS-141 4.5042E+02 4.5042E+02 1.7913E+02 1.7913E+02 0.0000E+00 0.0000E+00 51-SB-132 51-SB-132 8.2562E+01 8.2562E+01 1.6424E+02 1.6424E+02 0.0000E+00 0.0000E+00 45-RH-109 45-RH-109 1.1212E+02 1.1212E+02 1.1212E+02 1.1212E+02 0.0000E+00 0.0000E+00 42-MO-104 42-MO-104 2.7567E+02 2.7567E+02 2.7567E+02 2.7567E+02 0.0000E+00 0.0000E+00 35-BR-8735-BR-87 6.4339E+01 6.4339E+01 1.2606E+02 1.2606E+02 1.5438E-01 1.5438E-01 0.8%0.8%50-SN-130M 50-SN-130M 5.9192E+01 5.9192E+01 5.9192E+01 5.9192E+01 0.0000E+00 0.0000E+00 45-RH-108 45-RH-108 1.6500E+02 1.6500E+02 2.8228E+01 2.8228E+01 0.0000E+00 0.0000E+00 38-SR-95 38-SR-95 3.5834E+02 3.5834E+02 1.8146E+02 1.8146E+02 0.0000E+00 0.0000E+00 40-ZR-98 40-ZR-98 2.6260E+02 2.6260E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 57-LA-144 57-LA-144 4.3620E+02 4.3620E+02 7.3519E+02 7.3519E+02 0.0000E+00 0.0000E+00 43-TC-103 43-TC-103 2.5045E+02 2.5045E+02 6.3430E+01 6.3430E+01 0.0000E+00 0.0000E+00 37-RB-91 37-RB-91 1.8479E+02 1.8479E+02 2.6018E+02 2.6018E+02 0.0000E+00 0.0000E+00 35-BR-8835-BR-88 5.2561E+01 5.2561E+01 6.8342E+01 6.8342E+01 1.7717E-01 1.7717E-01 0.5%0.5%41-NB-99M 41-NB-99M 9.8816E+01 9.8816E+01 4.5403E+01 4.5403E+01 0.0000E+00 0.0000E+00 44-RU-107 44-RU-107 1.4108E+02 1.4108E+02 4.4947E+01 4.4947E+01 0.0000E+00 0.0000E+00 43-TC-105 43-TC-105 8.9851E+01 8.9851E+01 4.5860E+01 4.5860E+01 0.0000E+00 0.0000E+00 58-CE-147 58-CE-147 1.7679E+02 1.7679E+02 2.4018E+01 2.4018E+01 0.0000E+00 0.0000E+00 38-SR-94 38-SR-94 1.3388E+02 1.3388E+02 2.2935E+02 2.2935E+02 0.0000E+000.0000E+00

239239PuPuthth : 1 min : 1 minNuclide Nuclide Energy release rate eV per second per fission Energy release rate eV per second per fission Ebeta Ebeta Egamma Egamma EalphaEalpha36-KR-90 36-KR-90 1.0965E+02 1.0965E+02 1.0965E+02 1.0965E+02 0.0000E+00 0.0000E+00 35-BR-86 35-BR-86 8.0745E+01 8.0745E+01 1.3261E+02 1.3261E+02 0.0000E+00 0.0000E+00 43-TC-102 43-TC-102 1.1771E+02 1.1771E+02 4.8878E+00 4.8878E+00 0.0000E+00 0.0000E+00 56-BA-143 56-BA-143 1.6958E+02 1.6958E+02 1.6958E+02 1.6958E+02 0.0000E+00 0.0000E+00 54-XE-137 54-XE-137 2.4327E+02 2.4327E+02 2.7335E+01 2.7335E+01 0.0000E+00 0.0000E+00 37-RB-90 37-RB-90 6.2628E+01 6.2628E+01 6.0565E+01 6.0565E+01 0.0000E+00 0.0000E+00 41-NB-99 41-NB-99 1.9311E+02 1.9311E+02 2.2240E+01 2.2240E+01 0.0000E+00 0.0000E+00 58-CE-145 58-CE-145 6.4721E+01 6.4721E+01 5.1009E+01 5.1009E+01 0.0000E+00 0.0000E+00 56-BA-144 56-BA-144 6.0895E+01 6.0895E+01 6.0895E+01 6.0895E+01 0.0000E+00 0.0000E+00 38-SR-93 38-SR-93 3.3045E+01 3.3045E+01 9.2254E+01 9.2254E+01 0.0000E+00 0.0000E+00 58-CE-148 58-CE-148 7.6018E+01 7.6018E+01 7.6018E+01 7.6018E+01 0.0000E+00 0.0000E+00 ------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------Totals Totals 1.3073E+04 1.3073E+04 1.0055E+04 1.0055E+04 9.6049E+00 9.6049E+00

87.92% of all nuclides87.92% of all nuclides

239239PuPuthth : 1.1 h : 1.1 hNuclide Nuclide Energy release rate eV per second per fission Energy release rate eV per second per fission Ebeta Ebeta Egamma Egamma EalphaEalpha

53-I-134 53-I-134 4.2397E+00 4.2397E+00 1.7166E+01 1.7166E+01 0.0000E+00 0.0000E+00 12%12%51-SB-130 51-SB-130 8.3440E-01 8.3440E-01 3.6537E+00 3.6537E+00 0.0000E+00 0.0000E+00 2.5%2.5%57-LA-14357-LA-143 1.7144E+00 1.7144E+00 3.4970E-01 3.4970E-01 0.0000E+00 0.0000E+00 1.1%1.1%55-CS-138 55-CS-138 1.0023E+01 1.0023E+01 1.8952E+01 1.8952E+01 0.0000E+00 0.0000E+00 43-TC-104 43-TC-104 5.7022E+00 5.7022E+00 6.7564E+00 6.7564E+00 0.0000E+00 0.0000E+00 52-TE-134 52-TE-134 1.3600E+00 1.3600E+00 5.3068E+00 5.3068E+00 0.0000E+00 0.0000E+00 52-TE-133M 52-TE-133M 9.4822E-01 9.4822E-01 4.5968E+00 4.5968E+00 0.0000E+00 0.0000E+00 51-SB-131 51-SB-131 1.1401E+00 1.1401E+00 3.4346E+00 3.4346E+00 0.0000E+00 0.0000E+00 43-TC-101 43-TC-101 2.9988E+00 2.9988E+00 2.1049E+00 2.1049E+00 0.0000E+00 0.0000E+00 45-RH-107 45-RH-107 1.8601E+00 1.8601E+00 1.3425E+00 1.3425E+00 0.0000E+00 0.0000E+00 59-PR-146 59-PR-146 4.3807E+00 4.3807E+00 3.2848E+00 3.2848E+00 0.0000E+00 0.0000E+00 39-Y-94 39-Y-94 3.2132E+00 3.2132E+00 1.3535E+00 1.3535E+00 0.0000E+00 0.0000E+00 54-XE-138 54-XE-138 1.2126E+00 1.2126E+00 2.1231E+00 2.1231E+00 0.0000E+00 0.0000E+00 52-TE-133 52-TE-133 1.0299E+00 1.0299E+00 1.7949E+00 1.7949E+00 0.0000E+00 0.0000E+00 42-MO-101 42-MO-101 1.0980E+00 1.0980E+00 2.8780E+00 2.8780E+00 0.0000E+00 0.0000E+00 43-TC-102 43-TC-102 2.0989E+00 2.0989E+00 8.7154E-02 8.7154E-02 0.0000E+00 0.0000E+00 57-LA-142 57-LA-142 3.4813E+00 3.4813E+00 9.3213E+00 9.3213E+00 0.0000E+00 0.0000E+00 52-TE-131 52-TE-131 2.6906E+00 2.6906E+00 1.6273E+00 1.6273E+00 0.0000E+00 0.0000E+00 53-I -135 53-I -135 6.5360E-01 6.5360E-01 2.8157E+00 2.8157E+00 0.0000E+00 0.0000E+00

239239PuPuthth : 1.1 h : 1.1 hNuclide Nuclide Energy release rate eV per second per fission Energy release rate eV per second per fission Ebeta Ebeta Egamma Egamma EalphaEalpha44-RU-105 44-RU-105 1.0274E+00 1.0274E+00 1.8353E+00 1.8353E+00 0.0000E+00 0.0000E+00 56-BA-139 56-BA-139 4.7599E+00 4.7599E+00 2.4188E-01 2.4188E-01 0.0000E+00 0.0000E+00 55-CS-139 55-CS-139 8.8106E-01 8.8106E-01 1.8512E-01 1.8512E-01 0.0000E+00 0.0000E+00 56-BA-141 56-BA-141 2.3808E+00 2.3808E+00 2.1948E+00 2.1948E+00 0.0000E+00 0.0000E+00 36-KR-87 36-KR-87 8.7826E-01 8.7826E-01 5.2021E-01 5.2021E-01 0.0000E+00 0.0000E+00 35-BR-84 35-BR-84 4.3105E-01 4.3105E-01 6.1073E-01 6.1073E-01 0.0000E+00 0.0000E+00 37-RB-89 37-RB-89 5.2460E-01 5.2460E-01 1.2613E+00 1.2613E+00 0.0000E+00 0.0000E+00 36-KR-88 36-KR-88 1.9344E-01 1.9344E-01 1.0156E+00 1.0156E+00 0.0000E+00 0.0000E+00 38-SR-92 38-SR-92 2.2029E-01 2.2029E-01 1.6910E+00 1.6910E+00 0.0000E+00 0.0000E+00 37-RB-88 37-RB-88 1.0891E+00 1.0891E+00 3.5324E-01 3.5324E-01 0.0000E+00 0.0000E+00 59-PR-147 59-PR-147 5.9894E-01 5.9894E-01 5.9894E-01 5.9894E-01 0.0000E+00 0.0000E+00 57-LA-141 57-LA-141 1.8625E+00 1.8625E+00 5.1822E-02 5.1822E-02 0.0000E+00 0.0000E+00 39-Y-95 39-Y-95 7.2937E-01 7.2937E-01 5.5444E-01 5.5444E-01 0.0000E+00 0.0000E+00 60-ND-149 60-ND-149 5.3283E-01 5.3283E-01 3.9270E-01 3.9270E-01 0.0000E+00 0.0000E+00 56-BA-142 56-BA-142 2.6207E-01 2.6207E-01 6.8613E-01 6.8613E-01 0.0000E+00 0.0000E+00 59-PR-145 59-PR-145 5.3970E-01 5.3970E-01 5.3970E-01 5.3970E-01 0.0000E+00 0.0000E+00 ------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------Totals Totals 7.3672E+01 7.3672E+01 1.0695E+02 1.0695E+02 1.4742E-21 1.4742E-21

93.72% of all nuclides93.72% of all nuclides

239239PuPuthth : 1.04 d : 1.04 dNuclide Nuclide Energy release rate eV per second per fission Energy release rate eV per second per fission Ebeta Ebeta Egamma Egamma EalphaEalpha 53-I-135 53-I-135 5.2571E-02 5.2571E-02 2.2648E-01 2.2648E-01 0.0000E+00 0.0000E+00 10%10%54-XE-135 54-XE-135 1.2904E-01 1.2904E-01 1.0169E-01 1.0169E-01 0.0000E+00 0.0000E+00

8%8%53-I-133 53-I-133 1.1171E-01 1.1171E-01 1.6708E-01 1.6708E-01 0.0000E+00 0.0000E+00 51-SB-128 51-SB-128 1.3006E-02 1.3006E-02 8.1520E-02 8.1520E-02 0.0000E+00 0.0000E+00 46-PD-109 46-PD-109 4.2663E-02 4.2663E-02 7.6214E-05 7.6214E-05 0.0000E+00 0.0000E+00 53-I-132 53-I-132 4.6180E-02 4.6180E-02 2.0961E-01 2.0961E-01 0.0000E+00 0.0000E+00 41-NB-97M 41-NB-97M 2.6280E-03 2.6280E-03 1.3283E-01 1.3283E-01 0.0000E+00 0.0000E+00 39-Y-93 39-Y-93 1.2054E-01 1.2054E-01 9.7878E-03 9.7878E-03 0.0000E+00 0.0000E+00 41-NB-97 41-NB-97 9.6867E-02 9.6867E-02 1.3737E-01 1.3737E-01 0.0000E+00 0.0000E+00 52-TE-131M 52-TE-131M 2.5946E-03 2.5946E-03 1.9557E-02 1.9557E-02 0.0000E+00 0.0000E+00 58-CE-143 58-CE-143 6.5217E-02 6.5217E-02 4.2423E-02 4.2423E-02 0.0000E+00 0.0000E+00 44-RU-105 44-RU-105 2.4738E-02 2.4738E-02 4.4188E-02 4.4188E-02 0.0000E+00 0.0000E+00 40-ZR-97 40-ZR-97 1.3479E-01 1.3479E-01 3.0536E-02 3.0536E-02 0.0000E+00 0.0000E+00 45-RH-105 45-RH-105 3.7660E-02 3.7660E-02 1.8961E-02 1.8961E-02 0.0000E+00 0.0000E+00 38-SR-91 38-SR-91 3.9836E-02 3.9836E-02 4.3505E-02 4.3505E-02 0.0000E+00 0.0000E+00 39-Y-92 39-Y-92 4.4377E-02 4.4377E-02 7.7700E-03 7.7700E-03 0.0000E+00 0.0000E+00

239239PuPuthth : 1.04 d : 1.04 d

Nuclide Nuclide Energy release rate eV per second per fission Energy release rate eV per second per fission Ebeta Ebeta Egamma Egamma EalphaEalpha47-AG-112 47-AG-112 1.1879E-02 1.1879E-02 1.1879E-02 1.1879E-02 0.0000E+00 0.0000E+00 61-PM-151 61-PM-151 9.6357E-03 9.6357E-03 1.0384E-02 1.0384E-02 0.0000E+00 0.0000E+00 39-Y-91M 39-Y-91M 1.0409E-03 1.0409E-03 2.0919E-02 2.0919E-02 0.0000E+00 0.0000E+00 42-MO-99 42-MO-99 4.9636E-02 4.9636E-02 1.8711E-02 1.8711E-02 0.0000E+00 0.0000E+00 52-TE-132 52-TE-132 9.1510E-03 9.1510E-03 2.1116E-02 2.1116E-02 0.0000E+00 0.0000E+00 56-BA-140 56-BA-140 1.0619E-02 1.0619E-02 6.1590E-03 6.1590E-03 0.0000E+00 0.0000E+00 59-PR-145 59-PR-145 3.3915E-02 3.3915E-02 3.3915E-02 3.3915E-02 0.0000E+00 0.0000E+00 57-LA-141 57-LA-141 3.0254E-02 3.0254E-02 8.4176E-04 8.4176E-04 0.0000E+00 0.0000E+00 57-LA-140 57-LA-140 6.5668E-03 6.5668E-03 2.8380E-02 2.8380E-02 0.0000E+00 0.0000E+00 61-PM-149 61-PM-149 1.4410E-02 1.4410E-02 4.6664E-04 4.6664E-04 0.0000E+00 0.0000E+00 53-I-131 53-I-131 5.0711E-03 5.0711E-03 1.0055E-02 1.0055E-02 0.0000E+00 0.0000E+00 43-TC-99M 43-TC-99M 1.7541E-03 1.7541E-03 1.4329E-02 1.4329E-02 0.0000E+00 0.0000E+00 ------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------Totals Totals 1.2214E+00 1.2214E+00 1.5141E+00 1.5141E+00 3.3189E-19 3.3189E-19

95.01% of all nuclides95.01% of all nuclides

239239PuPuthth : 347 d : 347 dNuclide Nuclide Energy release rate eV per second per Energy release rate eV per second per

fission fission

Ebeta Ebeta Egamma Egamma EalphaEalpha 45-RH-106 45-RH-106 9.4740E-04 9.4740E-04 1.3713E-04 1.3713E-04 0.0000E+00 0.0000E+00

50%50%59-PR-144 59-PR-144 5.9896E-04 5.9896E-04 1.6843E-05 1.6843E-05 0.0000E+00 0.0000E+00

28%28%41-NB-95 41-NB-95 1.0723E-05 1.0723E-05 1.8411E-04 1.8411E-04 0.0000E+00 0.0000E+00 9%9%40-ZR-95 40-ZR-95 1.3718E-05 1.3718E-05 8.3745E-05 8.3745E-05 0.0000E+00 0.0000E+00 4.5%4.5%58-CE-144 58-CE-144 4.5510E-05 4.5510E-05 9.5041E-06 9.5041E-06 0.0000E+00 0.0000E+00 56-BA-137M 56-BA-137M 2.5771E-06 2.5771E-06 2.5393E-05 2.5393E-05 0.0000E+00 0.0000E+00 39-Y-91 39-Y-91 2.5415E-05 2.5415E-05 1.3141E-07 1.3141E-07 0.0000E+00 0.0000E+00 44-RU-103 44-RU-103 1.9349E-06 1.9349E-06 1.4423E-05 1.4423E-05 0.0000E+00 0.0000E+00 ------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------Totals Totals 1.7021E-03 1.7021E-03 4.7975E-04 4.7975E-04 2.2986E-15 2.2986E-15

97.05% of all nuclides97.05% of all nuclides

239239PuPuthth : 31.7 y : 31.7 y

Nuclide Nuclide Energy release rate eV per second per Energy release rate eV per second per fission fission

Ebeta Ebeta Egamma Egamma EalphaEalpha56-BA-137M 56-BA-137M 1.2680E-06 1.2680E-06 1.2494E-05 1.2494E-05 0.0000E+00 0.0000E+00

57%57%

39-Y-90 39-Y-90 5.0161E-06 5.0161E-06 6.6424E-12 6.6424E-12 0.0000E+00 0.0000E+00 21%21%

55-CS-137 55-CS-137 4.1552E-06 4.1552E-06 3.6367E-11 3.6367E-11 0.0000E+00 0.0000E+00 17%17%

38-SR-90 38-SR-90 9.3448E-07 9.3448E-07 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 4%4%

--------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------------

Totals Totals 1.1476E-05 1.1476E-05 1.2503E-05 1.2503E-05 1.0782E-14 1.0782E-14

99.53% of all nuclides99.53% of all nuclides

Decay Heat and Problem Fission Decay Heat and Problem Fission Products, December 2005, Products, December 2005, RWMRWM ++ ALNALN

8787BrBr 8989Sr, Sr, 9797Sr Sr 9898YYmm 100100Nb, Nb, 101101Nb, Nb, 102102Nb Nb 143143LaLa

8888Br Br 9393Rb, Rb, 9494Rb, Rb, 9595RbRb9999Y Y 137137I, I, 138138I, I, 139139II

Thanks: Decay HeatThanks: Decay Heat

Across the years:Across the years:

Alan Tobias (CEGB), at the beginning Alan Tobias (CEGB), at the beginning …………

Francois Storrer (CEA), in the middle Francois Storrer (CEA), in the middle agesages

Robert Mills (BNFL), over the recent pastRobert Mills (BNFL), over the recent past