US Commercial Spent 

Nuclear Fuel Assembly 

Characteristics: 1968-2013

Office of Nuclear Regulatory Research

NUREG/CR-7227

ORNL/TM-2015/619

US Commercial Spent 

Nuclear Fuel Assembly 

Characteristics: 1968-2013

Manuscript Completed: June 2016 

Date Published: September 2016

Prepared by: Jianwei Hu, Ian C. Gauld,

Joshua L. Peterson, and Stephen M. Bowman

Oak Ridge National Laboratory

Managed by UT-Battelle, LLC

Oak Ridge, TN 37831-6170

Mourad Aissa, NRC Project Manager

NRC Job Code Number V6449

Office of Nuclear Regulatory Research

NUREG/CR-7227

ORNL/TM-2015/619

iii

ABSTRACT

Activities related to management of spent nuclear fuel (SNF) are increasing in the US and many 

other countries. Over 240,000 SNF assemblies have been discharged from US commercial 

reactors since the late 1960s. The enrichment and burnup of SNF have changed significantly 

over the past 40 years, and fuel assembly designs have also evolved. Understanding the 

general characteristics of SNF helps regulators and other stakeholders form overall strategies 

towards the final disposal of US SNF. This report documents a survey of all US commercial 

SNF assemblies in the GC-859 database and provides reference SNF source terms (e.g., 

nuclide inventories, decay heat, and neutron/photon emission) at various cooling times up to 

200 years after fuel discharge. This study reviews the distribution and evolution of fuel 

parameters of all SNF assemblies discharged over the past 40 years. Assemblies were 

categorized into three groups based on discharge year, and the median burnups and 

enrichments of each group were used to establish representative cases. An extended burnup 

case was created for boiling water reactor (BWR) fuels, and another was created for the 

pressurized water reactor (PWR) fuels. Two additional cases were developed to represent the 

eight mixed oxide (MOX) fuel assemblies in the database. Burnup calculations were performed 

for each representative case. Realistic parameters for fuel design and operations were used to 

model the SNF and to provide reference fuel characteristics representative of the current 

inventory. Burnup calculations were performed using the ORIGEN code, which is part of the 

SCALE nuclear modeling and simulation code system. Results include total activity, decay heat, 

photon emission, neutron flux, gamma heat, and plutonium content, as well as concentrations 

for 115 significant nuclides. These quantities are important in the design, regulation, and 

operations of SNF storage, transportation, and disposal systems.

v

TABLE OF CONTENTS

ABSTRACT...................................................................................................................................iii

LIST OF FIGURES ......................................................................................................................vii

LIST OF TABLES......................................................................................................................... ix

ACKNOWLEDGMENTS .............................................................................................................. xi

LIST OF ACRONYMS.................................................................................................................xiii

1 INTRODUCTION ...................................................................................................................1

2 SURVEY OF US SPENT NUCLEAR FUEL AND CHARACTERISTICS...............................3

2.1 The GC-859 Database..................................................................................................3

2.2 Distribution of Fuel Enrichment, Burnup, and Lattice Type...........................................3

2.3 Evolution of Fuel Enrichment, Burnup, and Lattice Size...............................................8

2.4 Categorization of the Fuel Assemblies Based on Discharge Year .............................12

2.5 Representative Parameters for BWR, PWR, and MOX Groups .................................15

3 MODELING AND COMPUTATIONAL METHODS..............................................................17

3.1 TRITON and ORIGEN ................................................................................................17

3.2 Assembly Models........................................................................................................18

3.3 Fuel Composition and Operating History Data ...........................................................20

3.4 List of Significant Nuclides..........................................................................................20

4 SENSITIVITY OF INTEGRAL QUANTITIES TO FUEL PARAMETERS ............................23

4.1 Sensitivity to Burnup ...................................................................................................23

4.2 Sensitivity to Cooling Time .........................................................................................25

4.3 Sensitivity to Initial Enrichment ...................................................................................27

5 REFERENCE SOLUTIONS.................................................................................................29

5.1 Results in Appendixes ................................................................................................29

5.2 Activity ........................................................................................................................29

5.3 Decay Heat .................................................................................................................31

5.4 Gamma Heat ..............................................................................................................33

5.5 Photon Emission.........................................................................................................35

5.6 Neutron Flux ...............................................................................................................37

5.7 Plutonium Content ......................................................................................................39

5.8 Summary ....................................................................................................................41

6 SUMMARY AND CONCLUSIONS ......................................................................................45

7 REFERENCES....................................................................................................................47

APPENDIX A. BWR RESULTS ................................................................................................ A-1

APPENDIX B. PWR RESULTS ................................................................................................ B-1

APPENDIX C. MOX RESULTS ................................................................................................ C-1

APPENDIX D. ANALYSIS OF MAXIMUM ASSEMBLY DECAY HEAT.................................... D-1

vii

LIST OF FIGURES

Figure 1. Annual number of BWR (top) and PWR (bottom) fuel assemblies 

discharged. ................................................................................................................4

Figure 2. Number of BWR (left) and PWR (right) assemblies in three time periods as a 

function of initial enrichment (wt% 235U).....................................................................5

Figure 3. Number of BWR (left) and PWR (right) assemblies in three time periods as a 

function of assembly-average burnup........................................................................5

Figure 4. Number of assemblies (in one group) as a function of fuel burnup for BWR 

(top); and PWR (bottom)............................................................................................6

Figure 5. Distribution of total heavy metal mass (left) and total number of assemblies 

(right) for all BWR and PWR fuel assemblies in the GC-859 database.....................7

Figure 6. Distribution by lattice size for BWR (left) and PWR (right) assemblies......................8

Figure 7. Evolution of median initial enrichment as a function of fuel discharge year for 

all BWR (left) and PWR (right) assemblies................................................................9

Figure 8. Evolution of the median burnup as a function of fuel discharge year for all 

BWR (left) and PWR (right) assemblies...................................................................10

Figure 9. Evolution of assembly lattice size as a function of fuel discharge year for 

BWR (top) and PWR (bottom) assemblies. .............................................................11

Figure 10. Burnup and initial enrichment for each of the BWR (top) and PWR (bottom) 

assemblies in the GC-859 database........................................................................13

Figure 11. The TRITON/ORIGEN procedure used in this work to generate the 

reference solutions. .................................................................................................18

Figure 12. The TRITON models based on GE 8 × 8 and GE 10 × 10 fuel assembly 

lattice configurations. ...............................................................................................19

Figure 13. TRITON model based on W 17 × 17 fuel assembly lattice configuration. ...............19

Figure 14. Sensitivity of integral quantities to fuel burnup (results normalized to the 

case with the highest burnup)..................................................................................23

Figure 15. Sensitivity of Pu isotopes to fuel burnup..................................................................25

Figure 16. Sensitivity of integral quantities to cooling time (results normalized to the 

case with 5 years of cooling time)............................................................................26

Figure 17. Sensitivity of integral quantities to initial enrichment (values normalized to 

the case with 1.84% enrichment).............................................................................27

Figure 18. Activity as a function of cooling time for BWR assemblies. .....................................30

Figure 19. Activity as a function of cooling time for PWR assemblies. .....................................30

Figure 20. Activity as a function of cooling time for UO2 and MOX assemblies........................31

Figure 21. Decay heat as a function of cooling time for BWR assemblies................................32

Figure 22. Decay heat as a function of cooling time for PWR assemblies................................32

Figure 23. Decay heat as a function of cooling time for MOX assemblies................................33

Figure 24. Gamma energy release as a function of cooling time for BWR assemblies. ...........34

Figure 25. Gamma energy release as a function of cooling time for PWR assemblies. ...........34

Figure 26. Gamma energy release as a function of cooling time for MOX assemblies. ...........35

Figure 27. Photon emission as a function of cooling time for BWR assemblies. ......................36

Figure 28. Photon emission as a function of cooling time for PWR assemblies. ......................36

Figure 29. Photon emission as a function of cooling time for MOX assemblies. ......................37

Figure 30. Total neutron flux as a function of cooling time for BWR assemblies......................38

Figure 31. Total neutron flux as a function of cooling time for PWR assemblies......................39

Figure 32. Total neutron flux as a function of cooling time for MOX assemblies. .....................39

Figure 33. Pu total as a function of cooling time for BWR assemblies......................................40
viii

Figure 34. Pu isotopes as a function of cooling time for BWR-2...............................................40

Figure 35. Pu total as a function of cooling time for PWR assemblies......................................41

Figure 36. Pu total as a function of cooling time for PWR and MOX assemblies. ....................41

Figure 37. Summary for BWR assemblies (values normalized to the case with the 

highest burnup)........................................................................................................42

Figure 38. Summary for PWR and MOX assemblies................................................................44

Figure D.1. Assembly specific power (MW/MTU) for BWR (left) and PWR (right) 

assemblies from the US spent fuel inventory database GC-859 ........................... D-2

Figure D.2. Specific power distribution of PWR assemblies in each operating cycle for 

15 cycles of data (data below 33 MW/MTU is omitted).......................................... D-3
ix

LIST OF TABLES

Table 1. Number of BWR and PWR SNF assemblies in each burnup group. .....................7

Table 2. Summary of enrichment and burnup for each UO2 BWR and PWR group...........14

Table 3. Parameters of each of 8 MOX fuel assemblies in GC-859 ...................................15

Table 4. Representative parameters for each UO2 BWR and PWR group........................16

Table 5. Representative parameters for each MOX group .................................................16

Table 6. The top 20 contributing nuclides for decay heat, mass, and activity for 

PWR-2 with a cooling time of 5 years ...................................................................21

Table 7. Integral quantities as a function of fuel burnup (values based on 1 MTU)............24

Table 8. Integral quantities as a function of cooling time (values based on 1 MTU)..........26

Table 9. Integral quantities as a function of initial enrichment (values based on 1 

MTU).....................................................................................................................28

Table 10. Conversion factor used to convert neutron emission to neutron flux on 

assembly surface..................................................................................................37

Table 11. Summary for BWR assemblies (values based on 1 MTU)....................................43

Table 12. Summary for PWR and MOX assemblies (values based on 1 MTU) ...................44

Table A.1. Total activity (Ci/MTU) for BWR fuel................................................................... A-1

Table A.2. Total gamma heat (W/MTU) for BWR fuel .......................................................... A-1

Table A.3. Total decay heat (W/MTU) for BWR fuel ............................................................ A-1

Table A.4. Total photon emission (photon/sec/MTU) for BWR fuel...................................... A-2

Table A.5. Total neutron emission (neutron/sec/MTU) for BWR fuel ................................... A-2

Table A.6. Neutron flux (neutron/cm2-sec/MTU) for BWR fuel............................................. A-2

Table A.7. Pu total (gram/MTU) for BWR fuel...................................................................... A-3

Table A.8. Nuclide activities (Ci/MTU) for BWR-1 (22 GWd/MTU) ...................................... A-3

Table A.9. Nuclide activities (Ci/MTU) for BWR-2 (33 GWd/MTU) ...................................... A-6

Table A.10. Nuclide activities (Ci/MTU) for BWR-3 (44 GWd/MTU) ...................................... A-9

Table A.11. Nuclide activities (Ci/MTU) for BWR-Ext (72 GWd/MTU) ................................. A-12

Table A.12. Nuclide mass (gram/MTU) for BWR-1 (22 GWd/MTU)..................................... A-15

Table A.13. Nuclide mass (gram/MTU) for BWR-2 (33 GWd/MTU)..................................... A-19

Table A.14. Nuclide mass (gram/MTU) for BWR-3 (44 GWd/MTU)..................................... A-23

Table A.15. Nuclide mass (gram/MTU) for BWR-Ext (72 GWd/MTU).................................. A-27

Table B.1. Total activity (Ci/MTU) for PWR fuel................................................................... B-1

Table B.2. Total gamma heat (W/MTU) for PWR fuel.......................................................... B-1

Table B.3. Total decay heat (W/MTU) for PWR fuel ............................................................ B-1

Table B.4. Total photon emission (photon/s/MTU) for PWR fuel ......................................... B-2

Table B.5. Total neutron emission (neutron/s/MTU) for PWR fuel ....................................... B-2

Table B.6. Neutron flux (neutron/cm2-sec/MTU) for PWR fuel............................................. B-2

Table B.7. Pu total (gram/MTU) for PWR fuel...................................................................... B-3

Table B.8. Nuclide activities (Ci/MTU) for PWR-1 (28 GWd/MTU) ...................................... B-3

Table B.9. Nuclide activities (Ci/MTU) for PWR-2 (39 GWd/MTU) ...................................... B-5

Table B.10. Nuclide activities (Ci/MTU) for PWR-3 (47 GWd/MTU) ...................................... B-8

Table B.11. Nuclide activities (Ci/MTU) for PWR-Ext (72 GWd/MTU) ................................. B-10

Table B.12. Nuclide mass (gram/MTU) for PWR-1 (28 GWd/MTU)..................................... B-12

Table B.13. Nuclide mass (gram/MTU) for PWR-2 (39 GWd/MTU)..................................... B-16

Table B.14. Nuclide mass (gram/MTU) for PWR-3 (47 GWd/MTU)..................................... B-20

Table B.15. Nuclide mass (gram/MTU) for PWR-Ext (72 GWd/MTU).................................. B-24

Table C.1. Total activity (Ci/MTHM) for MOX fuel ................................................................ C-1

Table C.2. Total gamma heat (W/MTHM) for MOX fuel ....................................................... C-1
x

Table C.3. Total decay heat (W/MTHM) for MOX fuel.......................................................... C-1

Table C.4. Total photon emission (photon/s/MTHM) for MOX fuel....................................... C-1

Table C.5. Total neutron emission (neutron/s/MTHM) for MOX fuel .................................... C-2

Table C.6. Neutron flux (neutrons/cm2-sec/MTHM) for MOX fuel ........................................ C-2

Table C.7. Pu total (gram/MTHM) for MOX fuel ................................................................... C-2

Table C.8. Nuclide activity (Ci/MTHM) for MOX-1 (20 GWd/MTHM) ................................... C-2

Table C.9. Nuclide activity (Ci/MTHM) for MOX-2 (40 GWd/MTHM) ................................... C-5

Table C.10. Nuclide mass (gram/MTHM) for MOX-1 (20 GWd/MTHM)................................. C-7

Table C.11. Nuclide mass (gram/MTHM) for MOX-2 (40 GWd/MTHM)............................... C-11

Table D.1. Summary of assembly specific power values ..................................................... D-4

Table D.2. Scaling factors for the hottest assembly ............................................................. D-4
xi

ACKNOWLEDGMENTS

This work was supported by Office of Nuclear Regulatory Research, US Nuclear Regulatory 

Commission (NRC), under Project V6449, T0012, Technical Data for Extended Burnup Fuel –

Inclusion of US Department of Energy (DOE) GC-859 Data. The authors thank Ben Betzler of 

Oak Ridge National Laboratory for generating the ORIGEN libraries used in this report. The 

authors also express their appreciation for review of the manuscript by G. Ilas, J. J. Powers, and 

J. M. Scaglione at Oak Ridge National Laboratory, editing by R. B. Raney, and formatting by A. 

C. Alford. The authors would also like to thank the DOE Nuclear Fuels Storage and 

Transportation Planning Project (NFST) and the US Energy Information Administration (EIA) for 

providing access to the GC-859 database.

xiii

LIST OF ACRONYMS

BWR boiling water reactor

DOE US Department of Energy

DPA displacements per atom

EFPD effective full power day

EIA US Energy Information Administration

EOL end of life

Gd gadolinium

GE General Electric

GUI graphical user interface

GWd gigawatt days

ID identification

LWR light water reactor 

MOX mixed oxide fuel

MT metric ton

MTHM metric ton of heavy metal

MTU metric ton of uranium

NEI Nuclear Energy Institute

NFST Nuclear Fuels Storage and Transportation Planning Project

NRC US Nuclear Regulatory Commission

PWR pressurized water reactor

SNF spent nuclear fuel

UO2 uranium dioxide

W Westinghouse

wt% weight percent

1 

1 INTRODUCTION 

Activities related to management of spent nuclear fuel (SNF) are increasing in the US and many 

other countries. Storage of SNF is an important issue for the US nuclear industry and its 

regulators, as there is currently no decision on final disposal of SNF in the US. Since the late 

1960s, over 240,000 SNF assemblies have been discharged from US commercial reactors. The 

enrichment and burnup of the SNF have changed significantly over the past 40 years, and fuel 

assembly designs have evolved, as well. It is important to examine the variations of the SNF 

parameters and identify the general characteristics, which can help the SNF regulators and 

other stakeholders develop SNF management strategies. 

The GC-859 database [1], which is maintained by the US Energy Information Administration 

(EIA), documents information on every SNF assembly discharged from US commercial reactors 

from 1968 to 2013. This database provides a basis for evaluating the general characteristics of 

US SNF. An SNF assembly contains hundreds of nuclides in varying concentrations as 

determined by the assembly’s initial enrichment, burnup, cooling time, and the relevant reactor 

operation conditions. Nuclide concentrations and their associated radiological properties are 

important input parameters for the design and safety evaluation of SNF storage, transportation, 

and disposal systems. The goal of this study is twofold: (1) summarize the general US SNF 

characteristics by surveying the GC-859 database and (2) provide calculated reference 

solutions to SNF source terms based on these typical characteristics. 

This study surveys the GC-859 database, generates statistics on distributions of SNF 

parameters such as burnup and initial enrichment, and identifies the general trends of these 

parameters for all boiling water reactor (BWR) and pressurized water reactor (PWR) SNF 

assemblies documented in the database. Because these parameters have evolved over time, 

the SNF assemblies are divided into three groups based on the discharge year. BWR and PWR 

assemblies are grouped separately, with three groups for BWR assemblies and three groups for 

PWR assemblies. The median burnups and median initial enrichments for the assemblies in 

each group are used to represent the fuels in that group. The GC-859 database also contains 

information on eight mixed oxide (MOX) fuel assemblies which were discharged from two 

different PWRs. Two groups have been established to represent these MOX assemblies. 

Additionally, an extended burnup case with a burnup of 72 gigawatt days (GWd) per metric ton 

of uranium (MTU) and an enrichment of 5 weight percent (wt%) 235U is also included for BWR 

and PWR fuel. Although this burnup exceeds what can typically be achieved for an assembly 

with 5 wt% enrichment, it represents the upper bound for burnup of US fuel assemblies. 

This study also provides calculated reference solutions to SNF source terms using the 

representative SNF parameters identified in the first part. The source terms, including isotopic 

inventories, activities, decay heat, etc., were calculated in this work using the well-validated 

ORIGEN code [2] from the SCALE nuclear analysis code package [3]. In generating the 

reference solutions, calculations for PWRs were performed based on a Westinghouse (W) 

17 × 17 assembly design, and the General Electric (GE) 8 × 8 design was used for BWR 

calculations. W 14 × 14 and W 17 × 17 assembly designs were used for the MOX calculations. 

Studies were also conducted to quantify the sensitivities of the SNF source terms to burnup, 

cooling time, and initial enrichment of the fuel. 

Specifically, the reference solutions include the following SNF source terms: 

x activity, 

x decay heat, 
2 

x gamma heat, 

x photon emission, 

x neutron emission, 

x neutron flux on assembly surface, 

x plutonium content, 

x specific activities for a list of 69 nuclides (Section 3), and 

x specific concentrations for a list of 115 nuclides (Section 3). 

Most of the results are presented as a function of cooling time up to 200 years. Results are 

presented at cooling times relevant to fuel assembly discharge from a reactor, pool storage, 

interim dry cask storage, extended dry storage, and early stage of storage in a geological 

repository. The integral quantities presented in this report are of interest to the design, 

operation, and safety regulation of the SNF storage and transportation systems. For example, 

decay heat and gamma heat are important parameters for the system’s heat transfer design. 

Photon emission, neutron flux, and activity are the main considerations for radiation shielding 

design and worker protection of the SNF system. Plutonium content is important for evaluation 

of criticality safety, safeguards, and fuel cycles. 

This report is comprised of six sections and four appendixes. Section 2 presents the survey 

results of the database, Section 3 describes the computational methods and models used in this 

work, and Section 4 provides the sensitivity study results. Section 5 summarizes the reference 

solutions for UO2-based BWR and PWR fuels and for the MOX-based PWR fuels. (There is no 

BWR MOX fuel in the database.) Section 6 provides the summary and conclusions. Detailed 

results of the concentrations and activities for the significant nuclides are included in the 

appendixes. In response to a specific request from the sponsor, analysis of maximum assembly 

decay heat was also performed in this work and the results are presented in Appendix D. 

 
3 

2 SURVEY OF US SPENT NUCLEAR FUEL AND CHARACTERISTICS 

2.1 The GC-859 Database 

The GC-859 database is an extension of the previous RW-859 [4] database, and it also contains 

SNF discharged after 2002 up to 2013. Some survey results based on the RW-859 database 

are published elsewhere [5]. Both databases were developed and maintained by EIA. All 

generators or owners of SNF and high-level radioactive waste of domestic origin are required by 

law to provide relevant information to the database as specified in Form GC-859 [6]. The 

database contains detailed information about permanently discharged SNF assemblies and the 

associated reactor and cycle data. It also contains limited information about projected assembly 

discharges, pool storage, dry storage, canisters, and nonfuel components. Data on permanently 

discharged fuel were evaluated in this study. For each assembly, the database contains: 

x an assembly identifier (ID), 

x the initial uranium and plutonium mass and the initial enrichment (of 235U, 239Pu, and 

241Pu), 

x the discharge burnup, 

x the last irradiation cycle number, 

x the fuel vendor, 

x the assembly lattice type, 

x the assembly status code, and 

x the storage location. 

Unless identified otherwise, the enrichment and burnup used in this report refer to the average 

values of a given fuel assembly. The burnup is the final burnup after the assembly has been 

discharged from the reactor. 

2.2 Distribution of Fuel Enrichment, Burnup, and Lattice Type 

This section presents the statistics and distributions of fuel assemblies based on the survey 

results. Figure 1 shows the number of SNF assemblies discharged annually from BWRs and 

PWRs as a function of the discharge year. As shown, the number of discharged assemblies 

steadily increased up to the early 1990s as more reactors came into service. The current 

average discharge rates are ~4,100 assemblies per year for BWRs and ~3,300 assemblies per 

year for PWRs. (The number of reactors has not changed significantly since 1990.) The number 

of assemblies decreased sharply in 2013 because the data were incomplete for that year. In 

total there have been nearly 139,000 BWR assemblies discharged from the late 1960s to 2013, 

and over 105,000 PWR assemblies were discharged during the same period. 
4 

Figure 1. Annual number of BWR (top) and PWR (bottom) fuel assemblies discharged. 

Figure 2 shows the number of fuel assemblies as a function of initial enrichment for BWR (left) 

and PWR (right) assemblies. The data are divided into three time periods: 1968–1983, 

1984–2002, and 2003–2013. As shown, the average enrichment increases in later time groups. 

The figure also shows that enrichment varies within 2–4% for the majority of the BWR 

assemblies and 3–5% for PWR assemblies. 

0

500

1000

1500

2000

2500

3000

3500

4000

4500

5000

1969197219741976197819801982198419861988199019921994199619982000200220042006200820102012

Number of assemblies/year

Discharge year

BWR

0

1000

2000

3000

4000

1970197219741976197819801982198419861988199019921994199619982000200220042006200820102012

Number of assemblies/year

Discharge year

PWR
5 

Figure 2. Number of BWR (left) and PWR (right) assemblies in three time periods as a 

function of initial enrichment (wt% 235U). 

Figure 3 shows the number of assemblies as a function of fuel burnup in the same three time 

periods. It can be seen that the burnup increases in later time groups. 

Figure 3. Number of BWR (left) and PWR (right) assemblies in three time periods as a 

function of assembly-average burnup. 
6 

Figure 4 shows information similar to that shown in Figure 3 except that the data are not divided 

into time periods. As shown, the burnup varies within 20–50 GWd/MTU for the majority of BWR 

assemblies and 30–52 GWd/MTU for PWRs, although a few assemblies have extremely low or 

high burnups. Median burnups are 35 GWd/MTU for BWR assemblies and 42 GWd/MTU for 

PWR assemblies. 

Figure 4. Number of assemblies (in one group) as a function of fuel burnup for BWR 

(top); and PWR (bottom). 

Table 1 shows the number and percentage of BWR and PWR assemblies in several burnup 

intervals. As shown, for BWR, 25–35 and 35–45 are the top two burnup intervals for the number 

of assemblies; for PWR the intervals are 35–45 and 45–55. This indicates that BWR assemblies 

generally have lower burnups than PWR assemblies. Only 8 BWR assemblies reached burnups 

above 55 GWd/MTU, but the number is 1,307 for PWR assemblies. The total number of BWR 

and PWR assemblies with burnups higher than 55 GWd/MTU is only 0.54% among all 

assemblies in the GC-859 database. 

0

1000

2000

3000

4000

5000

6000

0 10 20 30 40 50 60 70

Number of assemblies

Burnup (GWd/MTU)

Median burnup: 

35 GWd/MTU BWR

0

1000

2000

3000

4000

5000

6000

0 10 20 30 40 50 60 70 80

Number of assemblies

Burnup (GWd/MTHM)

Median burnup: 

42 GWd/MTU PWR
7 

Table 1. Number of BWR and PWR SNF assemblies in each burnup group 

Burnup 

interval

(GWd/MTU) 

BWR PWR 

No. of 

assemblies 

Percent 

(%) 

No. of 

assemblies 

Percent 

(%) 

0–15 8,506 6.227 1,970 1.873 

15–25 20,033 14.665 6,662 6.334 

25–35 38,954 28.516 21,066 20.029 

35–45 47,171 34.531 38,876 36.962 

45–55 21,932 16.055 35,296 33.559 

55–65 6 0.004 1,303 1.239 

65–70 2 0.001 4 0.004 

Subtotals 136,604 100 105,177 100 

Figure 5 shows the distribution of total initial heavy metal mass between BWR and PWR 

assemblies (left) and the distribution for the total number of assemblies (right). There is 

significantly more heavy metal in the PWR assemblies in total than in the BWR assemblies, 

even though there are more BWR assemblies. This is because a PWR assembly usually 

contains more uranium than a BWR assembly. For example, a typical fresh 17 × 17 PWR 

assembly contains ~460 kg uranium, whereas an 8 × 8 BWR assembly only contains ~170 kg 

uranium. 

Total heavy metal mass Total number of assemblies 

Figure 5. Distribution of total heavy metal mass (left) and total number of assemblies 

(right) for all BWR and PWR fuel assemblies in the GC-859 database. 

PWR:

65%

BWR:

35% PWR: 

41%

BWR:

59%
8

Figure 6 shows the distribution of lattice sizes among BWR assemblies (left) and PWR

assemblies (right). As shown, for BWR lattice size, 8 × 8 has the largest percentage among all 

assemblies, followed by 10 × 10, 9 × 9, and 7 × 7. The other assembly designs include a 6 × 6 

lattice used in BWR Type 1 plant designs and an 11 × 11 lattice design used at the Big Rock 

Point reactor until 1997. For PWR lattice size, 17 × 17 has the largest percentage among all 

assemblies, followed by 15 × 15, 14 × 14, and 16 × 16. Note that within each lattice type, there 

are usually many different design variants, but this level of detail is not available in the GC-859 

database.

 BWR PWR

Figure 6. Distribution by lattice size for BWR (left) and PWR (right) assemblies.

2.3 Evolution of Fuel Enrichment, Burnup, and Lattice Size

Figure 7 depicts the variation of median fuel enrichment (the dots connected by lines) as a 

function of discharge year for all BWR and PWR assemblies. Also shown are the 5% and 95%

enrichment values to illustrate the range for 90% of the assemblies. It can be seen that the 

median enrichment in general increases over time, except for a significant decrease between 

1972 and 1975 for PWRs. This corresponds to a time period when many new reactors first start 

operations. The 5%–95% range is relatively small (1–1.5 percentage points) for most years 

except for a few years between 1975 and 1990, during which the 5% values significantly deviate 

from the median values. This is likely due to the low enriched fuel assemblies used in the initial 

cores when reactors started operation during that period. It should also be noted that the initial 

enrichment of commercial nuclear fuel in the US is currently limited to less than 5 wt% 235U. 

7 × 7

10%

8 × 8

9 × 9 45%

19%

10 × 10

25%

Other 

lattice 

designs: 

1%

14 × 14

16%

15 × 15

26%

16 × 16

13%

17 × 17

45%
9

Figure 7. Evolution of median initial enrichment as a function of fuel discharge year for 

all BWR (left) and PWR (right) assemblies.

Figure 8 shows the variation of median burnup as a function of discharge year for all BWR and 

PWR assemblies. The discharge burnup of fully burned fuel is correlated to the fuel’s initial 

enrichment because the amount of fissile materials in an assembly limits the burnup that can be 

achieved. Therefore, similar observations can be made for the evolution of burnup as for initial 

enrichment. The median burnup generally increases over time, and it is consistent with the trend 

of the median initial enrichment. 

Median value 95% value

5% value

95% value

5% value

Median value
10

Figure 8. Evolution of the median burnup as a function of fuel discharge year for all BWR 

(left) and PWR (right) assemblies.

Figure 9 shows the number of assemblies for each BWR (top) and PWR (bottom) assembly 

lattice size as a function of discharge year. For the BWR assemblies, the dominant lattice size 

changes over time. For example, 7 × 7 was the dominant lattice size from 1970 to 1979, then 

8 × 8 from 1980 to 1998, then 9 × 9 from 1999 to 2006, and 10 × 10 beyond 2006. For PWR 

assemblies (bottom), the predominant lattice size is 17 × 17. The number of assemblies with 

lattice sizes 15 × 15, 14 × 14, and 16 × 16 are similar over the last several decades. BWRs can 

use different lattice designs for the same reactor, which is not the case for PWR plants.

95% value 95% value

5% value

Median value Median value

5% value
11

Figure 9. Evolution of assembly lattice size as a function of fuel discharge year for 

BWR (top) and PWR (bottom) assemblies.
12

2.4 Categorization of the Fuel Assemblies Based on Discharge Year

To further characterize the enrichment and burnup of the fuel assemblies in the GC-859 

database, all assemblies are divided into three groups based on the time period in which they 

were discharged: 

• 1968–1983, 

• 1984–2002, and

• 2003–2013. 

Groups for the same time periods were established for BWR and PWR assemblies. (The 

selection of cutoff years for each group is somewhat arbitrary, but the three groups generally 

correspond to low, medium, and high enrichment and burnup, respectively, as shown in Figure 

7 and Figure 8.) Figure 10 shows burnup and enrichment of all fuel assemblies. Each point in 

this figure represents a single fuel assembly in the database. More points appear in the upper 

right region of the figure for later time groups, indicating that higher enrichment and burnup are 

used in more recently discharged fuels, which is consistent with what is shown in Figure 7 and 

Figure 8. It can also be seen that burnup generally increases with enrichment. A few assemblies 

significantly deviate from the general trend as a result of some nonroutine reactor operations. 

For example, some SNF assemblies with high enrichments and low burnups were observed 

from several plants that were shut down before reaching their expected lifetime. These 

assemblies were not fully burned before they were discharged due to the plant shutdown. When

leaking fuel rods are identified, the affected assemblies are removed from the core. If the 

affected assemblies are not repaired, they are permanently discharged before reaching their 

typical burnup. As shown in Figure 10, several assemblies reached burnups close to or above 

65 GWd/MTU. These assemblies may have been irradiated for a test program; however, details 

about these assemblies are not available in the database.
13

Figure 10. Burnup and initial enrichment for each of the BWR (top) and PWR (bottom) 

assemblies in the GC-859 database. 

Table 2 summarizes the fuel parameters for each group of assemblies. It shows the full range of 

the enrichment and burnup for each group, in addition to the median values and number of 

assemblies. The median values are significantly higher in later groups. The [5%, 95%] range is 

much smaller than the full range shown in the [min, median, max] columns, suggesting that the 

majority of the assemblies vary in a small range. This is consistent with what is shown in Figure 

10.
14

Table 2. Summary of enrichment and burnup for each UO2 BWR and PWR group

Group 

ID

Discharge 

year range

Enrichment (%) Enrichment (%) Burnup (GWd/tU) Burnup 

(GWd/tU) Number of 

assemblies [min, median, max] [5%, 95%] [min, median, max] [5%, 95%]

BWR-1 1968–1983 [0.71, 2.33, 3.94] [1.11, 2.75] [0.1, 21.7, 40.5] [9.2, 29.1] 21,539

BWR-2 1984–2002 [0.71, 3.00, 4.24] [1.76, 3.76] [1.6, 32.6, 65.2] [13.5, 43.2] 68,087

BWR-3 2003–2013 [1.43, 3.99, 4.43] [3.31, 4.21] [6.5, 44.1, 54.0] [34.4, 50.2] 46,978

Total # of BWR assemblies: 136,604

PWR-1 1968–1983 [0.71, 2.94, 4.94] [1.95, 4.00] [2.8, 28.3, 55.4] [13.5, 36.5] 13,628

PWR-2 1984–2002 [0.71, 3.61, 4.97] [2.40, 4.46] [2.4, 39.4, 69.5] [21.7, 50.1] 56,293

PWR-3 2003–2013 [0.30, 4.28, 4.96] [3.96, 4.80] [3.0, 47.1, 69.7] [35.7, 54.3] 35,256

Total # of PWR assemblies: 105,177

While MOX fuel has been widely used in Europe and Japan to make use of the plutonium 

resource recycled from spent UO2 fuels, it is not widely used in the US. MOX fuel was used in 

several demonstration projects in the 1960s and 1970s at several US nuclear power plants 

including San Onofre, Ginna, Dresden, Quad Cities, and Big Rock Point [7]. Some of those 

MOX fuels were not full MOX fuel assemblies but included a mix of MOX and UO2 fuel rods. A 

more recent test at the Catawba power station in 2005 included 4 MOX assemblies using 

weapons-grade plutonium. The GC-859 database only contains information for the 8 MOX 

assemblies from San Onofre and Catawba, as shown in Table 3. As shown, the four assemblies 

from each of the two PWR reactors have almost identical fuel parameters; therefore, one group 

is selected for each reactor, as discussed in the following subsection. Because fresh MOX fuel 

contains plutonium in addition to uranium, it has distinctly different characteristics in some SNF

source terms when compared to UO2 fuel, so MOX fuel is therefore included in this study.
15

Table 3. Parameters of each of 8 MOX fuel assemblies in GC-859

Reactor 

name

Initial 

U 

(kg)

Initial 

Pu 

(kg)

235U 

(wt%)

239Pu/Pu 

(wt%)

Fissile* 

(wt%)

Pu/heavy 

metal 

(wt%)

Burnup 

(GWd/MTHM)

Discharge 

year Lattice type

San 

Onofre

Unit 1

311.2 11.2 0.71 80.3 3.67 3.49 19.3 1973 14 × 14

311.2 11.2 0.71 80.3 3.67 3.49 19.6 1973 14 × 14

311.2 11.2 0.71 80.3 3.67 3.49 19.2 1973 14 × 14

311.2 11.2 0.71 80.3 3.67 3.49 19.1 1973 14 × 14

Catawba

Unit 1 446.1 20.4 0.25 94.1 4.36 4.37 40.1 2008 17 × 17

445.7 20.4 0.25 94.1 4.36 4.38 40.5 2008 17 × 17

445.7 20.4 0.25 94.0 4.35 4.37 40.2 2008 17 × 17

445.4 20.3 0.25 94.0 4.35 4.37 40.5 2008 17 × 17

*Fissile includes 235U, 239Pu, and 241Pu. 

2.5 Representative Parameters for BWR, PWR, and MOX Groups

Reference solutions are generated in this work based on representative fuel parameters. Table 

4 shows the median enrichment and burnup for each BWR and PWR group. In addition to the 

three groups described in the previous subsection, two extended burnup groups, BWR-Ext and 

PWR-Ext, are added; the extended groups have a burnup of 72 GWd/MTU and an enrichment 

of 5%. Table 5 shows the parameters for the two MOX groups. While MOX fuel can be used in 

either BWRs or PWRs, all of the MOX fuel assemblies listed in the GC-859 database are from 

PWRs. Therefore, unless specified otherwise, MOX fuel groups discussed in this report refer 

only to MOX fuel from PWRs, and the BWR and PWR fuel groups refer to UO2-based fuel. 

Burnup simulations are performed in this work using the representative parameters for each 

group to provide reference solutions for SNF source terms. 
16

Table 4. Representative parameters for each UO2 BWR and PWR group

Group ID Median enrichment Median burnup 

(wt% 235U) (GWd/MTU)

BWR-1 2.33 21.73

BWR-2 3.00 32.58

BWR-3 3.99 44.14

BWR-Ext 5.00 72.00

PWR-1 2.94 28.32

PWR-2 3.61 39.44

PWR-3 4.28 47.08

PWR-Ext 5.00 72.00

Table 5. Representative parameters for each MOX group

Group 

ID

Pu/heavy 

metal 

(wt%)

239Pu/Pu 

(wt%)

235U 

(wt%)

Fissile 

(wt%)

Burnup 

(GWd/MTHM)

MOX-1 3.49 80 0.71 3.67 20

MOX-2 4.37 94 0.25 4.36 40
17

3 MODELING AND COMPUTATIONAL METHODS

SCALE (version 6.1.3) was used in this work to generate the reference solutions. Specifically, 

the TRITON module in SCALE was used to generate the ORIGEN neutron cross section 

libraries, which were then used in ORIGEN standalone calculations. The following subsection 

provides a brief description of TRITON and ORIGEN in SCALE. 

3.1 TRITON and ORIGEN 

In the burnup process, the neutron flux and neutron spectrum of the nuclear system affect the 

evolution of the nuclide compositions during irradiation; in turn, the changes in composition 

affect the neutron flux and spectrum. The TRITON sequence in SCALE accounts for these 

interdependencies. To calculate the space-dependent neutron flux and spectrum, TRITON can 

call NEWT (a two-dimensional deterministic transport code) or KENO (a three-dimensional

Monte Carlo code) to perform neutron transport calculation. NEWT was used in this work 

because it runs much faster than KENO while retaining sufficient accuracies and avoiding 

stochastic uncertainties. For fuel irradiation, TRITON calls ORIGEN to perform the depletion 

and decay calculations. TRITON allows users to save the burnup-dependent assembly-average 

neutron cross sections. These cross sections can be used in the standalone ORIGEN 

calculations. Multiple TRITON cases are usually run beforehand to cover the parameter space 

(including enrichment and moderator density) and generate a set of ORIGEN cross section 

libraries. Customized cross section libraries are then generated by interpolating these 

pregenerated libraries using the specific parameter values for a particular ORIGEN case. The 

customized libraries were used in the ORIGEN calculations to generate the reference solution. 

An ORIGEN case takes only seconds to complete. This approach saves time by performing the 

normally time-consuming TRITON calculations beforehand. In addition, the accuracies are 

retained because the details of the TRITON models are preserved in the saved cross section

libraries. The procedure is shown in Figure 11.

The ORIGEN isotope depletion and decay code is widely used by researchers, regulators, 

industry, and universities for design, safety, and licensing analyses. ORIGEN has been 

extensively validated against measured SNF destructive assay data [8] [9]. Excellent agreement 

between ORIGEN calculations and measured decay heat values from SNF assemblies has also 

been observed [10].

In this work, a Python script was developed to generate the ORIGEN input files. The particular 

cycle history, moderator density, ORIGEN library, initial compositions, cooling time, etc., for 

each ORIGEN case can be specified. The desired output and formats can also be specified in 

this script to generate input files for the OPUS post-processing code in order to extract output

data. Once ORIGEN inputs are generated, SCALE is used to perform these calculations.
18

Figure 11. The TRITON/ORIGEN procedure used in this work to generate the 

reference solutions.

3.2 Assembly Models

Many different BWR and PWR fuel assembly designs have been used in the US over the past 

40 years, as shown in Figure 9. For BWRs, 8 × 8 was the most widely used lattice size 

historically, and 10 × 10 is the most widely used in recent years. For PWRs, 17 × 17 is the 

dominant lattice size. ORIGEN libraries for these lattices are available in SCALE version 6.1.3. 

However, these libraries were generated using ENDF/B-V cross sections. To apply more up-todate cross-section data for this study, TRITON models were developed to generate new

ENDF/B-VII.0-based ORIGEN libraries for these lattice designs. The updated libraries were 

generated using SCALE version 6.1.3.

Figure 12 illustrates the TRITON models for the GE 8 × 8 and 10 × 10 lattice configurations. As 

shown, the fuel rods, gadolinium (Gd) rods, water rods, cladding, and channel box are modeled 

in detail. Gd rods were modeled using multiple concentric rings to account for the gradients in 

nuclide compositions caused by the large neutron absorption and self-shielding of Gd. Figure 13

shows the TRITON model based on the W 17 × 17 lattice configuration. Fuel rods, guide tubes, 

and cladding are modeled in detail. Internal studies show that the results generated using the 

GE 8×8 ORIGEN library are similar to those generated using the GE 10 × 10 library. Therefore, 

the ORIGEN library based on the GE 8 × 8 configuration was used to generate the reference 

solutions for BWRs. ORIGEN library based on the W 17 × 17 configuration was used to 

generate the reference solutions for PWRs. Updated MOX libraries were also generated with 

ENDF/B-VII.0 cross sections using SCALE 6.1.3, and they are used in this work.

Libraries

Pregenerate the ORIGEN cross 

section libraries using TRITON for 

different fuel types, initial 

enrichments, and moderator 

densities with full details of fuel 

design and operating conditions 

ORIGEN

Perform depletion and 

decay calculations 

according to specific 

conditions and using 

customized libraries

Nuclide 

compositions

Neutron and 

photon source 

terms

Activity, decay 

heat, and more

Interpolate the libraries 

based on fuel type, 

specific burnup, 

enrichment, and 

moderator density

Provide cycle history, decay 

time, and initial fuel 

composition
19

 GE 8 × 8 GE 10 × 10

 fuel rods water rods Gd rods water rods 

Figure 12. The TRITON models based on GE 8 × 8 and GE 10 × 10 fuel assembly lattice 

configurations. 

Figure 13. TRITON model based on W 17 × 17 fuel assembly lattice configuration.
20

3.3 Fuel Composition and Operating History Data

As discussed in Section 3.1, specific information on fuel design and operating conditions is 

needed to perform burnup simulations. Initial fuel composition is an important fuel design 

parameter. Uranium in fresh fuel rods contains not only 238U and 235U, but also two lowabundance isotopes: 234U and 236U. If the 235U enrichment is known, the weight percentage of 

234U, 236U, and 238U are calculated using the following equations [11]: 

% 234U = 0.0089E

% 236U = 0.0046E

% 238U = 100.0000 – 1.0135E

where E = wt% of 235U (235U enrichment)

The GC-859 database contains cycle-by-cycle burnup values and cycle lengths for a large 

fraction of assemblies. The average specific power for BWR assemblies is 24 MW/MTU, and for 

PWRs it is 38 MW/MTU. For the reference solutions, representative burnup values are used for 

each group; the total irradiation time was obtained by dividing the final burnup by the specific 

power. Three reactor cycles with the same duration for each cycle were assumed for all 

reference cases, so each cycle represents 1⁄3 of the total irradiation time. The downtime between 

cycles was assumed to be 45 days based on an analysis of average plant refueling outage 

times between 1995 and 2013 [1].

Moderator density is another important parameter for burnup simulations because it has a large 

impact on the neutron spectrum and neutron cross sections. In the TRITON models used to 

generate ORIGEN libraries, an average water density of 0.723 g/cm3 with an average soluble 

boron concentration of 630 ppm was used for PWRs. For BWRs, an average water density of 

0.450 g/cm3, corresponding to approximately 40% void, was used in regions between the fuel 

pins, and a density of 0.7373 g/cm3 was used outside the fuel channel and in water rods. For 

simplification, it was assumed that control rods or control blades were not inserted in the 

assemblies during irradiation. 

3.4 List of Significant Nuclides

A study was conducted as part of this effort to determine the nuclides of high importance to 

applications in SNF storage, transportation, and disposal. The median burnup and enrichment 

of PWR-2 (shown in Table 4) was chosen for this study. ORIGEN calculations have been 

performed for this fuel group using cooling times of 2 hours, 5 years, and 200 years. In each 

calculation, the top 20 contributing nuclides for decay heat, isotopic mass, and activity were

identified and then combined into one list. Table 6 lists the top 20 nuclides for each category at 

5 years. As shown, the top 20 nuclides represent over 97% of total decay heat, mass, and 

activity. Lists of nuclides have been developed similarly for other cooling times. At short cooling 

times, the top 20 nuclides account for a smaller fraction (60–70% for the 2-hour case) of total 

decay heat and activity because many short-lived fission products are key contributors to decay 

heat and activity. 
21

Table 6. The top 20 contributing nuclides for decay heat, mass, and activity for PWR-2 

with a cooling time of 5 years

Decay heat Mass Activity

Nuclide Watts/MTU Nuclide Grams/MTU Nuclide Curies/MTU

90Y 4.29E+02 238U 9.36E+05 241Pu 1.16E+05

137mBa 4.11E+02 235U 7.98E+03 137Cs 1.11E+05

134Cs 3.77E+02 239Pu 5.53E+03 137mBa 1.05E+05

106Rh 2.07E+02 236U 4.77E+03 90Y 7.75E+04

137Cs 1.18E+02 136Xe 2.77E+03 90Sr 7.75E+04

144Pr 1.15E+02 240Pu 2.51E+03 147Pm 5.46E+04

238Pu 1.01E+02 134Xe 1.79E+03 134Cs 3.70E+04

244Cm 9.62E+01 144Nd 1.58E+03 106Rh 2.16E+04

90Sr 9.00E+01 138Ba 1.53E+03 106Ru 2.16E+04

154Eu 4.50E+01 139La 1.44E+03 144Pr 1.57E+04

241Am 3.96E+01 140Ce 1.43E+03 144Ce 1.57E+04

147Pm 2.00E+01 133Cs 1.33E+03 85Kr 8.52E+03

240Pu 1.77E+01 142Ce 1.33E+03 154Eu 5.01E+03

85Kr 1.28E+01 141Pr 1.31E+03 125Sb 3.12E+03

239Pu 1.07E+01 132Xe 1.30E+03 238Pu 3.04E+03

144Ce 1.03E+01 137Cs 1.28E+03 244Cm 2.75E+03

125Sb 9.87E+00 241Pu 1.12E+03 155Eu 2.23E+03

241Pu 3.69E+00 100Mo 1.10E+03 241Am 1.19E+03

155Eu 1.64E+00 98Mo 9.74E+02 125mTe 7.65E+02

106Ru 1.28E+00 97Mo 9.54E+02 240Pu 5.69E+02

Totala 2.12E+03 Total 1.00E+06 Total 6.81E+05

Subtotalb 99.8% Subtotal 97.8% Subtotal 99.8%

a Total includes contributions from all actinides and fission products in the fuel. b Subtotal is the percent contribution of nuclides listed in the table to the total.

This study also included significant nuclides identified in other studies. The 28 nuclides 

considered important to burnup credit studies [12] are provided in List 1 below. A list of 69 

nuclides (List 2) was considered important to accident consequence studies [13]. The activity 

from each of these nuclides will be explicitly listed in the appendix for each reference case. By 

combining these two lists with the top 20 contributors for PWR-2 at three different cooling times, 

an extended list of nuclides was determined, as shown in List 3 below. The mass of each 

nuclide on List 3 is included in the appendix for each reference case. 

• List 1: the 28 nuclides important to burnup credit studies [12]:

234U, 235U, 236U, 238U, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am, 243Am, 237Np, 95Mo 

99Tc, 101Ru, 103Rh, 109Ag, 133Cs, 143Nd, 145Nd, 147Sm, 149Sm, 150Sm, 151Sm, 152Sm, 151Eu, 153Eu, 155Gd
22

• List 2: the 69 nuclides important to accident consequence studies [13]:

241Am, 137mBa, 139Ba, 140Ba, 141Ce, 143Ce, 144Ce, 242Cm, 244Cm, 58Co‡

, 60Co‡, 134Cs, 136Cs, 137Cs, 131I, 132I, 133I, 134I, 135I, 85Kr, 85mKr, 87Kr, 88Kr, 140La, 141La, 142La, 99Mo, 95Nb, 97Nb, 97mNb, 147Nd, 239Np, 143Pr, 144Pr, 144mPr, 238Pu, 239Pu, 240Pu, 241Pu, 86Rb, 88Rb, 103mRh, 105Rh, 106Rh, 103Ru, 105Ru, 106Ru, 89Sr, 90Sr, 91Sr, 92Sr, 99mTc, 127Te, 127mTe, 129Te, 129mTe, 131Te, 131mTe, 132Te, 133Xe, 135Xe, 135mXe, 90Y, 91Y, 91mY, 92Y, 93Y, 95Zr, 97Zr

• List 3: the combined list of 115 significant nuclides (nuclides also included in List 2 are in red 

italic font):

109Ag, 241Am, 242Am, 242mAm, 243Am, 137Ba, 137mBa, 138Ba, 139Ba, 140Ba, 140Ce, 141Ce, 142Ce, 143Ce, 144Ce, 242Cm, 243Cm, 244Cm, 245Cm, 133Cs, 134Cs, 136Cs, 137Cs, 151Eu, 153Eu, 154Eu, 155Eu, 155Gd, 131I, 132I, 133I, 134I, 135I, 85Kr, 85mKr, 87Kr, 88Kr, 139La, 140La, 141La, 142La, 100Mo, 95Mo, 97Mo, 98Mo, 99Mo, 93mNb, 95Nb, 97Nb, 97mNb, 143Nd, 144Nd, 145Nd, 147Nd, 148Nd, 237Np, 239Np, 147Pm, 141Pr, 143Pr, 144Pr, 144mPr, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 86Rb, 88Rb, 103Rh,

103mRh, 105Rh, 106Rh, 101Ru, 103Ru, 105Ru, 106Ru, 125Sb, 147Sm, 149Sm, 150Sm, 151Sm, 152Sm, 89Sr, 90Sr, 91Sr, 92Sr, 99Tc, 99mTc, 125mTe, 127Te, 127mTe, 129Te, 129mTe, 131Te, 131mTe, 132Te, 234U, 235U, 236U, 238U, 132Xe, 133Xe, 134Xe, 135Xe, 135mXe, 136Xe, 90Y, 91Y, 91mY, 92Y, 93Y, 93Zr, 95Zr, 97Zr

 ‡ Note that 58Co and 60Co in SNF almost entirely originate from impurities in fuel assembly structural materials, and 

the Co impurity level varies by orders of magnitude over the past several decades. Only actinides and fission 

products in fuel materials were considered in this work. Therefore, both 58Co and 60Co are removed from List 3 and 

are not included in the results of this report.
23

4 SENSITIVITY OF INTEGRAL QUANTITIES 

TO FUEL PARAMETERS

As discussed in Section 2 (e.g., Table 2 and Figure 10), the fuel parameters of the BWR and 

PWR assemblies vary across a wide range. Sensitivity studies have been performed in this 

work to quantify how the integral quantities change with the varying parameters.

4.1 Sensitivity to Burnup

In order to quantify the sensitivity to burnup, a W17 × 17 PWR assembly with 3.61% enrichment 

(same enrichment as PWR-2 shown in Table 4) and a five-year cooling time was chosen for this 

study. Seven cases with burnup values of 5, 15, 25, 35, 45, 55, or 60 GWd/MTU were 

simulated. The integral quantities—including activity, gamma heat, decay heat, photon 

emission, neutron emission, and Pu total—were obtained from the outputs. Figure 14 shows the 

results normalized to the corresponding values of the 60 GWd/MTU case. Neutron emission has 

the steepest slope with burnup, followed by decay heat, gamma heat, photon emission, activity, 

and Pu total. At the 5-year cooling time, neutron emission is primarily from 244Cm and increases

with the ~4th power of the burnup; photon emission is mainly from 137Cs and is nearly linear with 

burnup. Plutonium builds up faster at low burnups and then plateaus at higher burnups due to 

the depletion of 239Pu. The absolute values of the calculated integral quantities are shown in 

Table 7.

Figure 14. Sensitivity of integral quantities to fuel burnup (results normalized to the case 

with the highest burnup).

0

20

40

60

80

100

0 20 40 60

Normalized values

Burnup (GWd/MTU)

activity

gamma heat

decay heat

photon emission

neutron emission

Pu total
24

Table 7. Integral quantities as a function of fuel burnup (values based on 1 MTU)

Burnup

GWd/MTU

Total 

activity

Total 

gamma heat

Total decay 

heat

Total 

photon 

emission

Total 

neutron 

emission

Total Pu

(Curies) (Watts) (Watts) (Photon/s) (Neutron/s) (Grams)

5 9.26E+04 6.10E+01 2.45E+02 1.48E+15 3.55E+05 2.32E+03

15 2.82E+05 2.27E+02 7.49E+02 4.60E+15 5.31E+06 5.59E+03

25 4.61E+05 4.40E+02 1.28E+03 7.90E+15 5.11E+07 7.82E+03

35 6.22E+05 6.85E+02 1.87E+03 1.13E+16 2.40E+08 9.42E+03

45 7.65E+05 9.50E+02 2.53E+03 1.48E+16 7.19E+08 1.06E+04

55 8.93E+05 1.22E+03 3.28E+03 1.82E+16 1.62E+09 1.16E+04

60 9.54E+05 1.36E+03 3.69E+03 1.99E+16 2.26E+09 1.20E+04

Figure 15 shows the change of Pu isotopic contents as a function of burnup. The 239Pu and 

240Pu are the top two isotopes in abundance. Although 241Pu accumulates at a faster rate than 

242Pu at lower burnups, its abundance is similar to that of 242Pu at high burnups. 

While 239Pu builds up quickly at low burnups, it remains nearly constant after the burnup 

reaches 30 GWd/MTU because its depletion rate increases due to the burn-out of 235U at higher 

burnups. However, 240Pu grows almost linearly with burnup. The sum of Pu isotopes, or Pu total, 

also increases continuously with burnup although, at high burnups it increases at a lower rate 

than at lower burnups.
25

Figure 15. Sensitivity of Pu isotopes to fuel burnup.

4.2 Sensitivity to Cooling Time

A study was conducted to quantify the sensitivity of integral quantities to cooling time. In this 

study, the burnup (39 GWd/MTU) and enrichment (3.61%) for PWR-2 were used. Nine different 

cooling times ranging from 5 hours to 200 years were simulated, and the results were obtained 

for each cooling time step. 

Figure 16 shows the normalized integral quantities for these cooling times. Each integral 

quantity at each cooling time step was normalized by its corresponding value at the end of the 

first cooling time step (5 hours). As shown, except for the Pu total, all other quantities decrease 

dramatically with cooling time. For example, the neutron emission decreases by 50% after 5

years, whereas the activity, gamma heat, decay heat, and photon emission decreases by 90% 

after about 3 months. The differences in decay rate are largely driven by the half-lives of the top 

contributing nuclides. The neutron emission mainly comes from decay of 242Cm with a half-life of 

160 days and 244Cm with a half-life of 18 years. At short cooling times, short-lived fission 

products are major contributors to activity, gamma heat, decay heat, and photon emission, and 

their half-lives range from seconds to weeks. This results in a rapid initial decrease of these 

quantities. The absolute values of the calculated integral quantities are shown in Table 8.

0

2000

4000

6000

8000

10000

12000

14000

0 10 20 30 40 50 60 70

Grams/MTU

Burnup (GWd/MTU)

Pu-238

Pu-239

Pu-240

Pu-241

Pu-242

Pu total

238Pu

239Pu

240Pu

241Pu

242Pu

Pu total
26

Figure 16. Sensitivity of integral quantities to cooling time (results normalized to the case 

with 5 years of cooling time).

Table 8. Integral quantities as a function of cooling time (values based on 1 MTU)

Cooling 

time

Total 

activity

Total 

gamma heat

Total decay 

heat

Total photon 

emission

Total 

neutron 

emission

Total Pu

(Curies) (Watts) (Watts) (Photon/s) (Neutron/s) (Grams)

5 hours 7.47E+07 1.67E+05 3.16E+05 3.39E+18 8.32E+08 1.01E+04

1 day 5.57E+07 1.14E+05 2.12E+05 2.47E+18 8.32E+08 1.02E+04

3 months 7.59E+06 1.21E+04 3.12E+04 2.09E+17 7.13E+08 1.02E+04

1 year 2.78E+06 2.83E+03 1.16E+04 7.14E+16 5.27E+08 1.02E+04

5 years 6.81E+05 7.89E+02 2.12E+03 1.27E+16 3.88E+08 9.94E+03

10 years 4.64E+05 4.23E+02 1.33E+03 7.09E+15 3.22E+08 9.70E+03

25 years 2.88E+05 2.43E+02 9.46E+02 4.41E+15 1.87E+08 9.23E+03

50 years 1.51E+05 1.33E+02 6.28E+02 2.48E+15 7.95E+07 8.90E+03

200 years 9.33E+03 4.80E+00 1.87E+02 1.74E+14 1.03E+07 8.64E+03

0.00

0.01

0.10

1.00

10.00

100.00

0 50 100 150 200

Normalized values

Cooling time (years)

activity

gamma heat

decay heat

photon emission

neutron emission

Pu total
27

4.3 Sensitivity to Initial Enrichment

A study was conducted to quantify the sensitivity of integral quantities to initial enrichment. In 

this study, burnup was fixed at 39 GWd/MTU, and the cooling time was fixed at 5 years. 

Enrichment was varied in the range 1.84%–5.0%, which is the range for the PWR-2 group 

shown in Table 2, using eight values. Figure 17 shows the variation of each integral quantity as 

a function of enrichment. Values were normalized to the corresponding values from the 1.84% 

enrichment case. As shown, except for neutron emission, all other quantities had small changes 

with enrichment. At this cooling time (5 years), fission products are the main contributors to 

activity, decay heat, gamma heat, and photon emission. These factors depend mainly on 

burnups and cooling times. For fuels with lower enrichments, higher fluences are required to 

reach the same burnup because of the lower fissile content, which leads to more neutron 

absorption of 238U and thus greater generation of transuranic nuclides, including Cm. Therefore, 

there are higher neutron emissions at lower enrichment, as 242Cm and 244Cm are the two main 

neutron emitters in SNF. This also explains why there is more Pu mass at lower enrichment, but 

the consumption rate on Pu fissile isotopes is also higher at lower enrichment due to the lower 

quantities of 235U (the other main fissile isotopes). Thus, Pu total increases at a lower rate than 

neutron emission at lower enrichment. The absolute values of the calculated integral quantities

are presented in Table 9.

Figure 17. Sensitivity of integral quantities to initial enrichment (values normalized to the 

case with 1.84% enrichment).

0

20

40

60

80

100

120

1.50 2.50 3.50 4.50 5.50

Normalized values

Initial enrichment (%)

activity

gamma heat

decay heat

photon emission

neutron emission

Pu total
28

Table 9. Integral quantities as a function of initial enrichment (values based on 1 MTU)

Enrichment

(%)

Total 

activity

Total gamma 

heat

Total decay 

heat

Total photon 

emission

Total neutron 

emission Total Pu

(Curies) (Watts) (Watts) (Photon/s) (Neutron/s) (Grams)

1.84 6.72E+05 8.66E+02 2.36E+03 1.33E+16 1.20E+09 1.03E+04

2.0 6.73E+05 8.59E+02 2.33E+03 1.32E+16 1.08E+09 1.03E+04

2.5 6.76E+05 8.37E+02 2.25E+03 1.31E+16 7.70E+08 1.01E+04

3.0 6.79E+05 8.15E+02 2.18E+03 1.29E+16 5.58E+08 1.00E+04

3.5 6.81E+05 7.94E+02 2.13E+03 1.28E+16 4.13E+08 9.95E+03

4.0 6.82E+05 7.74E+02 2.09E+03 1.26E+16 3.13E+08 9.91E+03

4.5 6.83E+05 7.57E+02 2.05E+03 1.25E+16 2.40E+08 9.88E+03

5.0 6.82E+05 7.42E+02 2.02E+03 1.23E+16 1.88E+08 9.86E+03

In summary, the sensitivity of the integral quantities to burnup, cooling time, and enrichment are 

quantified. The results show that all the integral quantities studied are sensitive to burnup, and 

they are also very sensitive to cooling time except for Pu total, which decreased by only ~15% 

over the first 200 years. For the sensitivity to initial enrichment, variations of all quantities except 

for neutron emission were within 20% over the range of initial enrichment studied here; the 

neutron emission decreased by ~80%. These results help illustrate how much these quantities 

change with the varying fuel parameters without the need to perform detailed simulations.
29

5 REFERENCE SOLUTIONS

Burnup calculations have been performed for each representative case, including all BWR, 

PWR, and MOX fuel groups shown in Table 4 and Table 5, with cooling times varying from 5 

hours to 200 years. The results for the integral quantities are illustrated as a function of cooling 

time and are presented in this section in the following order: 

• activity, 

• decay heat, 

• gamma heat, 

• photon emission, 

• neutron flux, and 

• Pu content. 

All results are based on 1 metric ton of initial heavy metal loading (MTHM). The mass unit MTU 

is interchangeable with MTHM in the context of UO2 fuel. These results can be converted to an 

assembly basis by multiplying the quantities by the actual initial loading of uranium or heavy 

metal of a given assembly. An 8 × 8 BWR assembly usually has an initial loading of ~0.17 MTU, 

while a 17 × 17 PWR assembly would have an initial loading of ~0.46 MTU. 

5.1 Results in Appendixes

Reference solutions for nuclides on Lists 2 and 3 are included in the appendixes. The values of 

the integral quantities are also tabulated and presented there. Also included in appendixes are 

the activities of the nuclides on List 2 and the mass of each nuclide on List 3 for each 

representative case at several cooling time steps. The results for BWR, PWR, and MOX are 

presented in Appendixes A, B, and C, respectively. (Descriptions of Lists 2 and 3 can be found 

in Section 3.4.) Appendix D includes results for maximum assembly decay heat analysis.

5.2 Activity

The total activities for the BWR, PWR, and MOX groups are shown in Figure 18, Figure 19 and

Figure 20, respectively. The results for PWRs were also included in the figure for the MOXs 

(Figure 20) for comparison. As shown, the total activities of all cases decrease by over 3 orders 

of magnitude in the first 200 years after discharge. Within each set, the differences in activity 

due to different burnups are small at short cooling times, but they become pronounced after ~2 

years of cooling time. The results for MOX fuel are similar to those for UO2 fuel with similar 

burnups (Figure 20). At longer cooling times, the contribution to activity from actinides and 

cesium isotopes becomes more significant. Actinides and cesium isotopes are increasingly 

accumulated at higher burnups, so greater activities are observed in fuel with higher burnups at 

longer cooling times, as shown in the following three figures. 
30

Figure 18. Activity as a function of cooling time for BWR assemblies.

Figure 19. Activity as a function of cooling time for PWR assemblies.

1E+3

1E+4

1E+5

1E+6

1E+7

1E+8

0.001 0.01 0.1 1 10 100

Activity (curies)

Cooling time (years)

BWR-1 (22 GWd/MTU)

BWR-2 (33 GWd/MTU)

BWR-3 (44 GWd/MTU)

BWR-Ext (72 GWd/MTU)

1E+3

1E+4

1E+5

1E+6

1E+7

1E+8

0.001 0.01 0.1 1 10 100

Activity (curies)

Cooling time (years)

PWR-1 (28 GWd/MTU)

PWR-2 (39 GWd/MTU)

PWR-3 (47 GWd/MTU)

PWR-Ext (72 GWd/MTU)
31

Figure 20. Activity as a function of cooling time for UO2 and MOX assemblies.

5.3 Decay Heat

The results of total decay heat for each set of BWR, PWR, and MOX assemblies are shown in

Figure 21, Figure 22, and Figure 23, respectively. The decay heat decreases by over 2 orders of 

magnitude in 200 years after discharge. The results are similar at short cooling times (<0.1 

year) among different burnups, but they begin to diverge at longer cooling times (>1 year) 

because the decay heat is mainly driven by different sets of nuclides that have different halflives. At longer cooling times, the relative contributions from actinides increase [14], and fuels 

with higher burnups have accumulated more actinides. Therefore, higher decay heat is 

observed at higher burnups, especially at longer cooling times. Because MOX fuel is initially 

loaded with Pu in addition to U, more actinides are usually generated in MOX during irradiation 

than in UO2 fuels with similar burnups. This explains why both MOX cases have higher decay 

heat than the PWR cases after a cooling time of ~30 years, even though MOX-1 has lower 

burnup than the two PWR cases (Figure 23). At short cooling times, both PWR and MOX have 

higher decay heat than BWR because it was assumed that they had higher power densities (as 

described in Sect. 3), and power densities have major impacts on short-term decay heat, 

especially near the end of irradiation. 

1E+3

1E+4

1E+5

1E+6

1E+7

1E+8

0.001 0.01 0.1 1 10 100

Activity (curies)

Cooling time (years)

PWR-1 (28 GWd/MTU)

PWR-2 (39 GWd/MTU)

MOX-1 (20 GWd/MTHM)

MOX-2 (40 GWd/MTHM)
32

Figure 21. Decay heat as a function of cooling time for BWR assemblies.

 

Figure 22. Decay heat as a function of cooling time for PWR assemblies.

1E+0

1E+1

1E+2

1E+3

1E+4

1E+5

1E+6

0.001 0.01 0.1 1 10 100

Decay heat (watts)

Cooling time (years)

BWR-1 (22 GWd/MTU)

BWR-2 (33 GWd/MTU)

BWR-3 (44 GWd/MTU)

BWR-Ext (72 GWd/MTU)

1E+0

1E+1

1E+2

1E+3

1E+4

1E+5

1E+6

0.001 0.01 0.1 1 10 100

Decay heat (watts)

Cooling time (years)

PWR-1 (28 GWd/MTU)

PWR-2 (39 GWd/MTU)

PWR-3 (47 GWd/MTU)

PWR-Ext (72 GWd/MTU)
33

Figure 23. Decay heat as a function of cooling time for MOX assemblies.

5.4 Gamma Heat

The gamma heat is the total energy of all emitted gamma rays from decay of radionuclides in an

SNF assembly. This value is the gamma component of the decay heat power. The absorbed 

dose rate in air is nearly proportional to the energy of the emitted photon over the energy range 

of 70 keV to about 4 MeV. The gamma heat is therefore closely related to the unshielded dose 

rate near an assembly. The results of gamma heat for each set of BWR, PWR, and MOX 

assemblies are shown in Figure 24, Figure 25, and Figure 26, respectively. The gamma heat 

decreases by four orders of magnitude in 200 years after discharge. After ~5 years of cooling 

time, the gamma radiation is mainly driven by the decay of 134Cs (2-year half-life), 137Cs (30-year 

half-life), and 154Eu (8.6-year half-life), and the gamma radiation for each increases with 

increasing burnup. Therefore, the gamma heat from fuel with higher burnups is higher than that 

from low burnup fuels at cooling times longer than ~5 years. The results for MOX fuel are similar 

to those for UO2 fuel with similar burnups. 

1E+0

1E+1

1E+2

1E+3

1E+4

1E+5

1E+6

0.001 0.01 0.1 1 10 100

Decay heat (watts)

Cooling time (years)

PWR-1 (28 GWd/MTU)

PWR-2 (39 GWd/MTU)

MOX-1 (20 GWd/MTHM)

MOX-2 (40 GWd/MTHM)
34

Figure 24. Gamma energy release as a function of cooling time for BWR assemblies.

Figure 25. Gamma energy release as a function of cooling time for PWR assemblies.

1E+0

1E+1

1E+2

1E+3

1E+4

1E+5

1E+6

0.001 0.01 0.1 1 10 100

Gamma heat (watts)

Cooling time (years)

BWR-1 (22 GWd/MTU)

BWR-2 (33 GWd/MTU)

BWR-3 (44 GWd/MTU)

BWR-Ext (72 GWd/MTU)

1E+0

1E+1

1E+2

1E+3

1E+4

1E+5

1E+6

0.001 0.01 0.1 1 10 100

Gamma heat (watts)

Cooling time (years)

PWR-1 (28 GWd/MTU)

PWR-2 (39 GWd/MTU)

PWR-3 (47 GWd/MTU)

PWR-Ext (72 GWd/MTU)
35

Figure 26. Gamma energy release as a function of cooling time for MOX assemblies.

5.5 Photon Emission

The results of total photon emission for each set of BWR, PWR, and MOX assemblies are 

shown in Figure 27, Figure 28, and Figure 29, respectively. This is the total number of photons 

emitted in all energy groups considered. The photon emission decreases by nearly 4 orders of 

magnitude in 200 years after discharge. The results are similar at short cooling times (<0.1 

year) among different burnups, but they begin to diverge at longer cooling times (>1 year). The 

photon emission is dominated by short-lived fission products at short cooling times, then by 

137Cs, 154Eu, and 134Cs at intermediate cooling times and by mainly 137Cs after ~5 years of 

cooling time. Generally, 137Cs, 154Eu, and 134Cs trend with burnup and thus lead to higher photon 

emission in fuels with higher burnups. MOX fuel produces a similar amount of photon emission 

as UO2 fuel with similar burnups. 

1E+0

1E+1

1E+2

1E+3

1E+4

1E+5

1E+6

0.001 0.01 0.1 1 10 100

Gamma heat (watts)

Cooling time (years)

PWR-1 (28 GWd/MTU)

PWR-2 (39 GWd/MTU)

MOX-1 (20 GWd/MTHM)

MOX-2 (40 GWd/MTHM)
36

Figure 27. Photon emission as a function of cooling time for BWR assemblies.

Figure 28. Photon emission as a function of cooling time for PWR assemblies.

1E+13

1E+14

1E+15

1E+16

1E+17

1E+18

1E+19

0.001 0.01 0.1 1 10 100

Photon emission (p/s)

Cooling time (years)

BWR-1 (22 GWd/MTU)

BWR-2 (33 GWd/MTU)

BWR-3 (44 GWd/MTU)

BWR-Ext (72 GWd/MTU)

1E+13

1E+14

1E+15

1E+16

1E+17

1E+18

1E+19

0.001 0.01 0.1 1 10 100

Photon emission (p/s)

Cooling time (years)

PWR-1 (28 GWd/MTU)

PWR-2 (39 GWd/MTU)

PWR-3 (47 GWd/MTU)

PWR-Ext (72 GWd/MTU)
37

Figure 29. Photon emission as a function of cooling time for MOX assemblies.

5.6 Neutron Flux

Neutron emissions can be calculated by ORIGEN, but certain applications require knowing the 

neutron flux on the outer surface of the assembly or at a certain distance from the fuel. Ideally, 

the energy-dependent neutron emission in each fuel pin of a given assembly at different axial 

nodes needs to be calculated, and then neutron transport calculations should be performed to 

estimate the probability that an emitted neutron travels through media and reaches a particular 

location of interest. Such detailed calculations are beyond the scope of this project. Therefore, 

assumptions are made in this work to estimate the neutron flux on the outer surface of the 

assembly in which the neutron emission and material content were assumed to be uniform 

across the whole assembly. Two neutron transport models have been developed using MAVRIC

(a module in SCALE) for BWR and PWR assembly designs. The PWR and MOX cases 

considered share the same model because they have the same geometry. In this calculation, an 

average neutron energy spectrum is used to represent the neutron spectra among emitted 

neutrons from SNF in both cases. With these calculations, factors for converting neutron 

emission to neutron flux (on assembly surface) are quantified and presented in Table 10.

Table 10. Conversion factor used to convert neutron emission to neutron flux on 

assembly surface

Fuel type

Conversion 

factor

(1/cm2)

BWR 6.05E-05

PWR 5.72E-05

MOX 5.72E-05

1E+13

1E+14

1E+15

1E+16

1E+17

1E+18

1E+19

0.001 0.01 0.1 1 10 100

Photon emission (p/s)

Cooling time (years)

PWR-1 (28 GWd/MTU)

PWR-2 (39 GWd/MTU)

MOX-1 (20 GWd/MTHM)

MOX-2 (40 GWd/MTHM)
38

After multiplying the total neutron emissions by these conversion factors, the neutron flux for 

each case is calculated and illustrated in Figure 30, Figure 31, and Figure 32 for BWR, PWR, 

and MOX, respectively. Unlike the integral quantities shown previously, the neutron flux is very 

sensitive to burnup at all cooling times (instead of just at longer cooling times). The primary 

neutron emitter in SNF is 244Cm (18 year half-life), and the contribution from 242Cm (160-day 

half-life) is significant at short cooling times (<2 years). In addition, contributions from 240Pu

spontaneous fission and (α, n) reaction can be significant (~10%) in fuels with low burnup (<~20 

GWd/MTU) [15]. Note that the content of both 242Cm and 240Pu (6,563-year half-life) increases

nearly linearly with burnup, whereas that of 244Cm increases with nearly to the 4th power of 

burnup. The combined dependence on burnup of these three neutron emitters explains the 

large difference in neutron flux among the 4 cases with different burnups in each plot. The total 

neutron flux decreases by less than 2 orders of magnitude (much less than other integral 

quantities shown previously), which is due to the relative long half-lives of 244Cm and 240Pu. As 

shown in Figure 32, MOX produces much higher neutron flux than UO2 fuel (by a factor of ~ 5) 

with similar burnups, mainly because MOX fuel is initially loaded with Pu and thus has greater 

accumulations of higher actinides, including curium, after irradiation. 

Figure 30. Total neutron flux as a function of cooling time for BWR assemblies.

1E+1

1E+2

1E+3

1E+4

1E+5

1E+6

0.001 0.01 0.1 1 10 100

Neutron flux (n/cm2-s)

Cooling time (years)

BWR-1 (22 GWd/MTU)

BWR-2 (33 GWd/MTU)

BWR-3 (44 GWd/MTU)

BWR-Ext (72 GWd/MTU)
39

Figure 31. Total neutron flux as a function of cooling time for PWR assemblies.

Figure 32. Total neutron flux as a function of cooling time for MOX assemblies.

5.7 Plutonium Content

The Pu totals (the sum of isotopic contents for all Pu isotopes) as calculated by ORIGEN for 

BWR, PWR, and MOX assemblies are illustrated in Figure 33, Figure 35, and Figure 36, 

respectively. Because 239Pu and 240Pu, the two most abundant Pu isotopes, have long half-lives, 

the Pu total decreases by only 10–20% in 200 years after discharge. The decrease is mainly 

caused by the decay of 241Pu (14-year half-life). While 238Pu has a relatively short half-life (87.7 

years), its abundance is relatively small. As the sensitivity study shows in Section 4, the 

1E+2

1E+3

1E+4

1E+5

1E+6

0.001 0.01 0.1 1 10 100

Neutron flux (n/cm2-s)

Cooling time (years)

PWR-1 (28 GWd/MTU)

PWR-2 (39 GWd/MTU)

PWR-3 (47 GWd/MTU)

PWR-Ext (72 GWd/MTU)

1E+2

1E+3

1E+4

1E+5

1E+6

0.001 0.01 0.1 1 10 100

Neutron flux (n/cm2-s)

Cooling time (years)

PWR-1 (28 GWd/MTU)

PWR-2 (39 GWd/MTU)

MOX-1 (20 GWd/MTHM)

MOX-2 (40 GWd/MTHM)
40

amounts of all Pu isotopes increase with burnup, except that 239Pu plateaus at high burnup. 

These three plots show that the cases with higher burnups have much higher Pu totals. The Pu 

total of MOX fuel is ~3 times higher than that of UO2 fuel with similar burnups (Figure 36), 

because MOX fuel is initially loaded with a significant amount of Pu. Figure 34 shows the Pu 

isotopic masses from BWR-2 as a function of cooling time. As expected, 241Pu and 238Pu 

decrease significantly, and 239Pu, 240Pu, and 242Pu remain nearly constant over the 200 years of 

cooling time. The combined masses of 239Pu and 240Pu account for more than 80% of the total 

Pu mass. 

Figure 33. Pu total as a function of cooling time for BWR assemblies.

Figure 34. Pu isotopes as a function of cooling time for BWR-2.

0.0E+0

2.0E+3

4.0E+3

6.0E+3

8.0E+3

1.0E+4

1.2E+4

1.4E+4

0.001 0.01 0.1 1 10 100

Pu total (grams)

Cooling time (years)

BWR-1 (22 GWd/MTU)

BWR-2 (33 GWd/MTU)

BWR-3 (44 GWd/MTU)

BWR-Ext (72 GWd/MTU)

1.0E-2

1.0E-1

1.0E+0

1.0E+1

1.0E+2

1.0E+3

1.0E+4

0.001 0.01 0.1 1 10 100

Mass of Pu isotopes (grams)

Cooling time (years)

Pu-238

Pu-239

Pu-240

Pu-241

Pu-242

Pu total
41

Figure 35. Pu total as a function of cooling time for PWR assemblies.

Figure 36. Pu total as a function of cooling time for PWR and MOX assemblies.

5.8 Summary

Figure 37 summarizes the integral quantities of all BWR cases analyzed in this effort. These

results correspond to 5 years of cooling time, and they are normalized to the highest burnup 

0.0E+0

2.0E+3

4.0E+3

6.0E+3

8.0E+3

1.0E+4

1.2E+4

1.4E+4

0.001 0.01 0.1 1 10 100

Pu total (grams)

Cooling time (years)

PWR-1 (28 GWd/MTU)

PWR-2 (39 GWd/MTU)

PWR-3 (47 GWd/MTU)

PWR-Ext (72 GWd/MTU)

0.0E+0

5.0E+3

1.0E+4

1.5E+4

2.0E+4

2.5E+4

3.0E+4

3.5E+4

0.001 0.01 0.1 1 10 100

Pu total (grams)

Cooling time (years)

PWR-1 (28 GWd/MTU)

PWR-2 (39 GWd/MTU)

MOX-1 (20 GWd/MTHM)

MOX-2 (40 GWd/MTHM)
42

case. As shown, all integral quantities trend with burnup but at different rates. Gamma heat, 

decay heat, and photon emission have similar distributions among the four different cases. 

Neutron flux has the steepest dependence on burnup. Pu total has the flattest dependence on 

burnup, followed by activity. Table 11 includes the absolute values of the integral quantities 

shown in this figure.

Figure 37. Summary for BWR assemblies (values normalized to the case with the 

highest burnup).

0

20

40

60

80

100

activity gamma heat decay heat photon

emission

neutron flux Pu total

Normalized values (%)

BWR-1 (22 GWd/MTU)

BWR-2 (33 GWd/MTU)

BWR-3 (44 GWd/MTU)

BWR-Ext (72 GWd/MTU)
43

Table 11. Summary for BWR assemblies (values based on 1 MTU)

Unit BWR-1 BWR-2 BWR-3 BWR-Ext

Activity Curies 3.82E+05 5.37E+05 6.80E+05 9.94E+05

Gamma heat Watts 3.75E+02 5.99E+02 8.13E+02 1.39E+03

Decay heat Watts 1.07E+03 1.63E+03 2.18E+03 3.91E+03

Photon emission Photon/s 6.54E+15 9.74E+15 1.28E+16 2.04E+16

Neutron flux N/cm2-s 4.53E+03 1.62E+04 3.16E+04 1.56E+05

Pu total Gram 6.96E+03 8.39E+03 9.50E+03 1.16E+04

Figure 38 summarizes the integral quantities of two PWR cases and two MOX cases. These 

results correspond to 5 years of cooling time, and they are normalized to the highest burnup 

MOX case. As shown, the first four integral quantities—activity, gamma heat, decay heat, and 

photon emission—trend with burnup, and their dependence on burnup is similar to the BWR 

cases. However, for neutron flux and Pu total, MOX fuel has much higher quantities than UO2

fuel with similar burnups. Table 12 includes the absolute values of the integral quantities shown 

in Figure 38.
44

Figure 38. Summary for PWR and MOX assemblies.

Table 12. Summary for PWR and MOX assemblies (values based on 1 MTU)

Unit PWR-1 PWR-2 MOX-1 MOX-2

Activity Curies 5.14E+05 6.84E+05 5.79E+05 9.03E+05

Gamma heat Watts 5.37E+02 8.01E+02 3.68E+02 8.61E+02

Decay heat Watts 1.49E+03 2.14E+03 1.52E+03 2.51E+03

Photon 

emission Photon/s 9.06E+15 1.27E+16 6.50E+15 1.30E+16

Neutron flux N/cm2-s 9.04E+03 2.52E+04 5.64E+04 8.24E+04

Pu total Gram 8.98E+03 1.06E+04 2.90E+04 2.91E+04

0

10

20

30

40

50

60

70

80

90

100

activity gamma heat decay heat photon

emission

neutron flux Pu total

Normalized values

PWR-1 (28 GWd/MTU)

PWR-2 (39 GWd/MTU)

MOX-1 (20 GWd/MTHM)

MOX-2 (40 GWd/MTHM)
45

6 SUMMARY AND CONCLUSIONS

This report documents a survey of all US commercial SNF assemblies in the GC-859 database 

and provides SNF reference source terms (e.g., nuclide inventories, decay heat, and 

neutron/photon emission). These reference source terms were calculated using ORIGEN for 

cooling times up to 200 years and using representative fuel parameters based on the survey 

results. 

Based on the survey, the following observations are made regarding to the distribution and 

evolution of fuel parameters among all fuel assemblies in the database:

• The GC-859 database contains over 240,000 SNF assemblies discharged up to 2013, 59% 

of which are BWR assemblies. There are 8 MOX assemblies, all with a PWR lattice design.

• The number of assemblies discharged each year has remained nearly constant since 1990. 

The average annual discharge rate is ~4,100 assemblies per year for BWR and ~3,300 

assemblies per year for PWR.

• The most widely used BWR lattice configuration is 8 × 8 (historically) and 10 × 10 

(currently), followed by 9 × 9 and 7 × 7. The most widely used PWR lattice configuration is 

17 × 17, followed by 15 × 15, 16 × 16, and 14 × 14.

• In general, the median burnup and enrichment of the SNF has increased steadily over time, 

although enrichment is limited to less than 5% by NRC regulations, which in turn limits the 

maximum burnup a fuel assembly can achieve.

• Among all discharged assemblies, the median enrichment is 3.21% for BWR and 3.93% for 

PWR, and the median burnup is 35 GWd/MTU for BWR and 42 GWd/MTU for PWR. 

• Approximately 84% of the BWR assemblies and 65% of the PWR assemblies have burnups

less than 45 GWd/MTU. Only 19 BWR assemblies and 1307 PWR assemblies have 

burnups above 55 GWd/MTU, accounting for 0.54% of all BWR and PWR assemblies in the 

database. 

• Dividing all assemblies into three groups based on their discharge year provides a good 

platform to assess the evolution of the considered fuel parameters. It can be seen that on 

average, higher enrichment and burnup are observed in more recently discharged fuel. 

• The median burnup and enrichment of each group are identified and used as representative 

input parameters to generate the reference solutions. 

• Two representative MOX cases are identified to represent the 8 MOX assemblies in the 

database that were discharged from two different reactors. 

ORIGEN calculations were performed for each representative case for BWR, PWR and MOX 

assemblies using new ORIGEN libraries based on ENDF/B-VII.0 cross section data. 

Calculations were also performed for extended BWR and PWR burnup cases. The total activity, 

decay heat, gamma heat, photon emission, neutron flux, and Pu content are illustrated in this 

report; the activity and nuclide concentrations for a list of significant nuclides are included in the 

appendixes. The following observations can be made regarding these results:

• Neutron emission/flux has the highest dependence on fuel burnup, followed by activity, 

gamma heat, decay heat, photon emission, and Pu total. Gamma heat, decay heat, and 

photon emission have similar dependence on burnup.

• Activity, gamma heat, decay heat and photon emission all decrease rapidly with cooling time 

by over 3 orders of magnitude in 200 years after discharge. 
46

• Neutron flux decreases by nearly 2 orders of magnitude over 200 years due to the relatively 

longer half-lives of the top emitters. Pu total decreases by only 10–20% in 200 years after 

discharge, although 238Pu and 241Pu decease dramatically over time.

• MOX fuel produces results similar to UO2 fuel in activity, gamma heat, photon emission, and 

decay heat. However, there is much more Pu and higher neutron emission/flux in spent 

MOX fuel than in UO2 fuel. 

The survey of the GC-859 database provides a complete picture for the distribution and 

evolution of the fuel parameters of fuel assemblies in the US commercial fuel inventory. It helps 

the regulator and other stakeholders to form overall strategies towards the final disposal of US

SNF. The reference solutions generated in this work provide specific values for each of the 

integral quantities under representative scenarios, and these quantities are important 

considerations in the design, regulation, and operations of the SNF storage, transportation, and 

disposal systems.
47

7 REFERENCES

[1] U.S. Energy Information Administration, Form GC-859, "Nuclear Fuel Data Survey," 2013. 

[2] I. C. Gauld, G. Radulescu, G. Ilas, B. D. Murphy, M. L. Williams and D. Wiarda, "Isotopic 

Depletion and Decay Methods and Analysis Capabilities in SCALE," Nucl. Technol., vol. 

174, no. 2, pp. 169-195, 2011. 

[3] S. M. Bowman, "SCALE 6: Comprehensive Nuclear Safety Analysis Code System," 

Nuclear Technology, vol. 174, no. 2, pp. 126–148, 2011. 

[4] RW-859 Nuclear Fuel Data, Washington, D.C.: U.S. Energy Information Administration, 

2004. 

[5] J. Peterson and J. Wagner, "Characteristics of Commercial Spent Nuclear Fuel: 

Distributed, Diverse, and Changing with Time," RadWaste Solutions, no. January-March 

2014, pp. 50–58, 2014. 

[6] "Nuclear Fuel Data Survey Form GC-859," Energy Information Administration (EIA), U.S. 

Department of Energy, [Online]. Available: 

http://www.eia.gov/survey/form/gc_859/proposed/form.pdf. [Accessed 6/27/2016].

[7] "Mixed Oxide Fuel," 2016. [Online]. Available: http://www.world-nuclear.org/info/NuclearFuel-Cycle/Fuel-Recycling/Mixed-Oxide-Fuel-MOX/. [Accessed 6/27/2016].

[8] G. Radulescu, I. Gauld and G. Ilas, SCALE 5.1 Predictions of PWR Spent Nuclear Fuel 

Isotopic Compositions, Oak Ridge National Laboratory, ORNL/TM-2010/44, 2010.

[9] G. Ilas, I. C. Gauld and G. Radulescu, "Validation of new depletion capabilities and 

ENDF/B-VII data libraries in SCALE," Annals of Nuclear Energy, vol. 46, pp. 43–55, 2012. 

[10] G. Ilas, I. C. Gauld and H. Liljenfeldt, "Validation of ORIGEN for LWR used fuel decay heat 

analysis with SCALE," Nuclear Engineering and Design, vol. 273, pp. 58–67, 2014. 

[11] O. W. Hermann, C. V. Parks and J. P. Renier, Technical Support for a Proposed Decay 

Heat Guide Using SAS2H/ORIGEN-S Data, NUREG/CR-5625 (ORNL-6698), Oak Ridge 

National Laboratory, Oak Ridge, TN, 1994.

[12] C. V. Parks, M. D. DeHart and J. C. Wagner, Review and Prioritization of Technical Issues 

Related to Burnup Credit for LWR Fuel, NUREG/CR-6665, Oak Ridge National Laboratory, 

Oak Ridge, TN, 2000.

[13] J. A. Rollstin, D. I. Chanin and H.-N. Jow, MELCOR Accident Consequence Code System 

(MACCS), Nuclear Regulatory Commission, NUREG/CR-4691 Vol.3, 2007.

[14] I. C. Gauld and B. D. Murphy, "Technical Basis for a Proposed Expansion of Regulatory 

Guide 3.54 - Decay Heat Generation in an Independent Spent Fuel Storage Installation," 

NUREG/CR-6999, Oak Ridge National Laboratory, Oak Ridge, TN, 2010.

[15] J. Richard, M. L. Fensin and S. J. Tobin, "Characterization and Analysis of the Neutron 

Source Term of Spent PWR Fuel," in Institute of Nuclear Materials Management 51st 

Annual Meeting, Baltimore, MD, USA, 2010. 

A-1

APPENDIX A. BWR RESULTS

Table A.1. Total activity (Ci/MTU) for BWR fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 ye

BWR-1 

(22GWd/MTU) 4.64E+07 3.45E+07 4.54E+06 1.58E+06 3.82E+05 2.61E+05 8.50E+04 2.71E

BWR-2

(33GWd/MTU) 4.73E+07 3.53E+07 5.01E+06 1.94E+06 5.37E+05 3.77E+05 1.24E+05 3.96E

BWR-3 

(44GWd/MTU) 4.74E+07 3.54E+07 5.35E+06 2.20E+06 6.80E+05 4.88E+05 1.63E+05 5.21E

BWR-Ext 

(72GWd/MTU) 5.02E+07 3.78E+07 5.95E+06 2.76E+06 9.94E+05 7.29E+05 2.49E+05 8.00E

Table A.2. Total gamma heat (W/MTU) for BWR fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

BWR-1 

(22GWd/MTU) 1.04E+05 7.04E+04 7.09E+03 1.36E+03 3.75E+02 2.23E+02 7.52E+01 2.39E+0

BWR-2 

(33GWd/MTU) 1.06E+05 7.20E+04 7.84E+03 1.96E+03 5.99E+02 3.41E+02 1.11E+02 3.54E+0

BWR-3 

(44GWd/MTU) 1.07E+05 7.31E+04 8.53E+03 2.51E+03 8.13E+02 4.56E+02 1.46E+02 4.64E+0

BWR-Ext 

(72GWd/MTU) 1.12E+05 7.83E+04 1.03E+04 4.09E+03 1.39E+03 7.42E+02 2.31E+02 7.30E+0

Table A.3. Total decay heat (W/MTU) for BWR fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

BWR-1 

(22GWd/MTU) 1.97E+05 1.30E+05 1.80E+04 6.23E+03 1.07E+03 6.91E+02 3.36E+02 1.82E+0

BWR-2 

(33GWd/MTU) 2.01E+05 1.35E+05 2.07E+04 7.95E+03 1.63E+03 1.07E+03 5.05E+02 2.68E+0

BWR-3 

(44GWd/MTU) 2.03E+05 1.37E+05 2.27E+04 9.29E+03 2.18E+03 1.48E+03 6.78E+02 3.50E+0

BWR-Ext 

(72GWd/MTU) 2.13E+05 1.48E+05 2.76E+04 1.31E+04 3.91E+03 2.71E+03 1.15E+03 5.57E+0
A-2

Table A.4. Total photon emission (photon/sec/MTU) for BWR fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

BWR-1 

(22GWd/MTU) 2.11E+18 1.53E+18 1.23E+17 3.85E+16 6.54E+15 3.87E+15 1.40E+15 4.80E+1

BWR-2 

(33GWd/MTU) 2.14E+18 1.56E+18 1.36E+17 4.85E+16 9.74E+15 5.78E+15 2.06E+15 7.00E+1

BWR-3 

(44GWd/MTU) 2.13E+18 1.56E+18 1.46E+17 5.61E+16 1.28E+16 7.69E+15 2.71E+15 9.16E+1

BWR-Ext 

(72GWd/MTU) 2.27E+18 1.68E+18 1.69E+17 7.60E+16 2.04E+16 1.21E+16 4.15E+15 1.39E+1

Table A.5. Total neutron emission (neutron/sec/MTU) for BWR fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

BWR-1 

(22GWd/MTU) 2.51E+08 2.51E+08 2.00E+08 1.21E+08 7.49E+07 6.29E+07 1.82E+07 7.29E+0

BWR-2 

(33GWd/MTU) 6.48E+08 6.47E+08 5.43E+08 3.80E+08 2.68E+08 2.23E+08 5.63E+07 1.62E+0

BWR-3 

(44GWd/MTU) 1.09E+09 1.09E+09 9.41E+08 7.05E+08 5.23E+08 4.34E+08 1.06E+08 2.79E+0

BWR-Ext 

(72GWd/MTU) 4.06E+09 4.06E+09 3.76E+09 3.27E+09 2.58E+09 2.12E+09 5.14E+08 1.38E+0

Table A.6. Neutron flux (neutron/cm2

-sec/MTU) for BWR fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

BWR-1 

(22GWd/MTU) 1.52E+04 1.52E+04 1.21E+04 7.32E+03 4.53E+03 3.81E+03 1.10E+03 4.41E+0

BWR-2 

(33GWd/MTU) 3.92E+04 3.91E+04 3.29E+04 2.30E+04 1.62E+04 1.35E+04 3.41E+03 9.80E+0

BWR-3 

(44GWd/MTU) 6.59E+04 6.59E+04 5.69E+04 4.27E+04 3.16E+04 2.63E+04 6.41E+03 1.69E+0

BWR-Ext 

(72GWd/MTU) 2.46E+05 2.46E+05 2.27E+05 1.98E+05 1.56E+05 1.28E+05 3.11E+04 8.35E+0
A-3

Table A.7. Pu total (gram/MTU) for BWR fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

BWR-1 

(22GWd/MTU) 7.06E+03 7.07E+03 7.11E+03 7.09E+03 6.96E+03 6.82E+03 6.38E+03 6.29E+0

BWR-2 

(33GWd/MTU) 8.55E+03 8.56E+03 8.60E+03 8.57E+03 8.39E+03 8.21E+03 7.61E+03 7.48E+0

BWR-3 

(44GWd/MTU) 9.70E+03 9.71E+03 9.75E+03 9.71E+03 9.50E+03 9.29E+03 8.57E+03 8.41E+0

BWR-Ext 

(72GWd/MTU) 1.19E+04 1.19E+04 1.19E+04 1.19E+04 1.16E+04 1.14E+04 1.05E+04 1.03E+0

Table A.8. Nuclide activities (Ci/MTU) for BWR-1 (22 GWd/MTU)

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

am241 8.44E+01 8.47E+01 1.16E+02 2.12E+02 6.61E+02 1.11E+03 2.40E+03 2.43E+03 

ba137m 6.64E+04 6.64E+04 6.61E+04 6.49E+04 5.92E+04 5.28E+04 2.10E+04 6.64E+03 

ba139 1.08E+05 7.96E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.11E+06 1.06E+06 8.43E+03 2.72E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce141 1.06E+06 1.04E+06 1.56E+05 4.44E+02 1.34E-11 1.69E-28 0.00E+00 0.00E+00 

ce143 8.87E+05 5.95E+05 2.05E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 7.81E+05 7.80E+05 6.28E+05 3.22E+05 9.22E+03 1.09E+02 4.08E-14 0.00E+00 

cm242 2.30E+04 2.29E+04 1.58E+04 4.89E+03 1.15E+01 1.67E+00 1.37E+00 1.07E+00 

cm244 6.19E+02 6.19E+02 6.14E+02 5.96E+02 5.12E+02 4.22E+02 9.15E+01 1.35E+01 

cs134 7.40E+04 7.39E+04 6.81E+04 5.29E+04 1.38E+04 2.59E+03 3.85E-03 2.01E-10 

cs136 2.16E+04 2.07E+04 1.91E+02 9.77E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 7.02E+04 7.02E+04 6.98E+04 6.86E+04 6.25E+04 5.57E+04 2.22E+04 7.02E+03 

i131 6.56E+05 6.19E+05 2.92E+02 1.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 9.22E+05 7.75E+05 3.37E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.16E+06 6.17E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 8.37E+04 3.31E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 7.52E+05 1.01E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 6.76E+03 6.76E+03 6.65E+03 6.34E+03 4.90E+03 3.55E+03 2.70E+02 1.08E+01 

kr85m 7.47E+04 3.94E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
A-4

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

kr87 2.08E+04 6.57E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 1.21E+05 1.17E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la140 1.15E+06 1.13E+06 9.71E+03 3.13E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 4.76E+05 1.65E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.17E+05 2.00E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo99 1.15E+06 9.39E+05 1.69E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb95 1.04E+06 1.04E+06 6.60E+05 4.36E+04 6.10E-03 1.60E-11 0.00E+00 0.00E+00 

nb97 9.44E+05 4.04E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 8.40E+05 3.82E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd147 4.14E+05 3.93E+05 1.43E+03 4.12E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

np239 1.36E+07 1.08E+07 7.79E+00 7.79E+00 7.79E+00 7.79E+00 7.76E+00 7.72E+00 

pr143 9.77E+05 9.67E+05 1.10E+04 8.70E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 7.81E+05 7.80E+05 6.28E+05 3.22E+05 9.22E+03 1.09E+02 4.08E-14 0.00E+00 

pr144m 7.46E+03 7.45E+03 6.00E+03 3.07E+03 8.80E+01 1.04E+00 3.89E-16 0.00E+00 

pu238 9.05E+02 9.07E+02 9.48E+02 9.98E+02 9.91E+02 9.53E+02 6.95E+02 4.69E+02 

pu239 2.55E+02 2.56E+02 2.59E+02 2.59E+02 2.59E+02 2.59E+02 2.59E+02 2.58E+02 

pu240 4.17E+02 4.17E+02 4.17E+02 4.17E+02 4.17E+02 4.17E+02 4.16E+02 4.14E+02 

pu241 8.16E+04 8.16E+04 8.06E+04 7.77E+04 6.40E+04 5.03E+04 7.23E+03 6.41E+02 

rb86 8.48E+02 8.24E+02 3.00E+01 1.08E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.36E+05 1.31E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103m 1.05E+06 1.03E+06 2.14E+05 1.66E+03 1.05E-08 1.06E-22 0.00E+00 0.00E+00 

rh105 6.76E+05 4.99E+05 3.28E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 3.54E+05 3.54E+05 2.99E+05 1.79E+05 1.18E+04 3.92E+02 5.92E-10 9.89E-25 

ru103 1.06E+06 1.04E+06 2.16E+05 1.68E+03 1.07E-08 1.07E-22 0.00E+00 0.00E+00 

ru105 3.61E+05 1.86E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 3.54E+05 3.54E+05 2.99E+05 1.79E+05 1.18E+04 3.92E+02 5.92E-10 9.89E-25 

sr89 5.69E+05 5.63E+05 1.66E+05 3.82E+03 7.66E-06 1.03E-16 0.00E+00 0.00E+00 

sr90 5.02E+04 5.02E+04 4.99E+04 4.90E+04 4.45E+04 3.94E+04 1.51E+04 4.52E+03 

sr91 5.10E+05 1.30E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 2.22E+05 1.72E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
A-5

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

tc99m 1.05E+06 9.02E+05 1.63E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te127 5.88E+04 5.45E+04 2.58E+03 4.49E+02 4.17E-02 3.80E-07 0.00E+00 0.00E+00 

te127m 4.28E+03 4.30E+03 2.63E+03 4.58E+02 4.25E-02 3.88E-07 0.00E+00 0.00E+00 

te129 1.19E+05 2.47E+04 3.11E+03 1.07E+01 8.88E-13 0.00E+00 0.00E+00 0.00E+00 

te129m 3.14E+04 3.09E+04 4.93E+03 1.69E+01 1.41E-12 6.28E-29 0.00E+00 0.00E+00 

te131 3.18E+04 2.08E+04 9.53E-16 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 1.18E+05 7.92E+04 3.63E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 8.93E+05 7.52E+05 3.27E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe133 1.27E+06 1.23E+06 1.07E+01 1.74E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135 5.23E+05 3.20E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 1.29E+05 1.74E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y90 5.23E+04 5.19E+04 4.99E+04 4.90E+04 4.45E+04 3.95E+04 1.51E+04 4.53E+03 

y91 7.45E+05 7.41E+05 2.58E+05 9.94E+03 3.06E-04 1.25E-13 0.00E+00 0.00E+00 

y91m 3.28E+05 8.36E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 5.57E+05 2.54E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 6.64E+05 1.82E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr95 1.05E+06 1.04E+06 3.97E+05 2.02E+04 2.77E-03 7.27E-12 0.00E+00 0.00E+00 

zr97 8.83E+05 4.02E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Totala 4.64E+07 3.45E+07 4.54E+06 1.58E+06 3.82E+05 2.61E+05 8.50E+04 2.71E+04 

Subtotalb 93.5% 95.1% 96.5% 92.4% 88.5% 95.0% 99.6% 99.3% 

a Total includes contributions from all actinides and fission products in the fuel. b Subtotal is the percent contribution of nuclides listed in the table to the total.
A-6

Table A.9. Nuclide activities (Ci/MTU) for BWR-2 (33 GWd/MTU)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

am241 1.47E+02 1.48E+02 1.91E+02 3.20E+02 9.29E+02 1.54E+03 3.29E+03 3.32E+03 

ba137m 9.83E+04 9.83E+04 9.77E+04 9.60E+04 8.76E+04 7.81E+04 3.11E+04 9.82E+03 

ba139 1.07E+05 7.89E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.10E+06 1.05E+06 8.33E+03 2.69E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce141 1.05E+06 1.03E+06 1.54E+05 4.38E+02 1.32E-11 1.67E-28 0.00E+00 0.00E+00 

ce143 8.70E+05 5.84E+05 2.01E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 8.37E+05 8.36E+05 6.73E+05 3.45E+05 9.88E+03 1.17E+02 4.37E-14 0.00E+00 

cm242 4.60E+04 4.59E+04 3.15E+04 9.79E+03 2.27E+01 2.96E+00 2.42E+00 1.89E+00 

cm244 2.29E+03 2.29E+03 2.27E+03 2.20E+03 1.89E+03 1.56E+03 3.38E+02 4.99E+01 

cs134 1.35E+05 1.35E+05 1.25E+05 9.67E+04 2.53E+04 4.73E+03 7.04E-03 3.67E-10 

cs136 3.20E+04 3.07E+04 2.82E+02 1.45E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 1.04E+05 1.04E+05 1.03E+05 1.01E+05 9.25E+04 8.24E+04 3.28E+04 1.04E+04 

i131 6.58E+05 6.21E+05 2.92E+02 1.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 9.22E+05 7.75E+05 3.37E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.16E+06 6.14E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 8.27E+04 3.26E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 7.50E+05 1.01E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 9.55E+03 9.55E+03 9.40E+03 8.96E+03 6.92E+03 5.02E+03 3.82E+02 1.53E+01 

kr85m 7.07E+04 3.74E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 1.95E+04 6.18E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 1.14E+05 1.10E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la140 1.15E+06 1.13E+06 9.60E+03 3.10E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 4.70E+05 1.63E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.16E+05 1.97E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo99 1.14E+06 9.36E+05 1.68E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb95 1.04E+06 1.04E+06 6.50E+05 4.29E+04 5.99E-03 1.58E-11 0.00E+00 0.00E+00 

nb97 9.32E+05 3.99E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 8.29E+05 3.77E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd147 4.12E+05 3.92E+05 1.42E+03 4.11E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
A-7

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

np239 1.36E+07 1.07E+07 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.95E+01 

pr143 9.57E+05 9.48E+05 1.08E+04 8.53E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 8.37E+05 8.36E+05 6.73E+05 3.45E+05 9.88E+03 1.17E+02 4.37E-14 0.00E+00 

pr144m 7.99E+03 7.98E+03 6.43E+03 3.29E+03 9.43E+01 1.11E+00 4.17E-16 0.00E+00 

pu238 2.11E+03 2.11E+03 2.19E+03 2.29E+03 2.27E+03 2.18E+03 1.59E+03 1.07E+03 

pu239 2.78E+02 2.79E+02 2.82E+02 2.82E+02 2.82E+02 2.82E+02 2.82E+02 2.81E+02 

pu240 5.38E+02 5.38E+02 5.38E+02 5.38E+02 5.39E+02 5.39E+02 5.41E+02 5.38E+02 

pu241 1.11E+05 1.11E+05 1.09E+05 1.05E+05 8.68E+04 6.81E+04 9.80E+03 8.69E+02 

rb86 1.30E+03 1.26E+03 4.60E+01 1.66E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.27E+05 1.23E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103m 1.09E+06 1.07E+06 2.22E+05 1.73E+03 1.09E-08 1.10E-22 0.00E+00 0.00E+00 

rh105 7.17E+05 5.29E+05 3.47E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 4.48E+05 4.48E+05 3.79E+05 2.27E+05 1.49E+04 4.97E+02 7.49E-10 1.25E-24 

ru103 1.10E+06 1.08E+06 2.25E+05 1.75E+03 1.11E-08 1.11E-22 0.00E+00 0.00E+00 

ru105 3.82E+05 1.97E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 4.48E+05 4.48E+05 3.79E+05 2.27E+05 1.49E+04 4.97E+02 7.49E-10 1.25E-24 

sr89 5.34E+05 5.28E+05 1.56E+05 3.58E+03 7.18E-06 9.64E-17 0.00E+00 0.00E+00 

sr90 7.27E+04 7.27E+04 7.22E+04 7.09E+04 6.44E+04 5.71E+04 2.18E+04 6.55E+03 

sr91 4.82E+05 1.23E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 2.12E+05 1.64E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99m 1.05E+06 8.99E+05 1.62E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te127 6.02E+04 5.58E+04 2.70E+03 4.69E+02 4.36E-02 3.97E-07 0.00E+00 0.00E+00 

te127m 4.48E+03 4.51E+03 2.75E+03 4.79E+02 4.45E-02 4.06E-07 0.00E+00 0.00E+00 

te129 1.22E+05 2.52E+04 3.18E+03 1.09E+01 9.08E-13 0.00E+00 0.00E+00 0.00E+00 

te129m 3.21E+04 3.16E+04 5.04E+03 1.73E+01 1.44E-12 6.42E-29 0.00E+00 0.00E+00 

te131 3.20E+04 2.10E+04 9.60E-16 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 1.19E+05 7.99E+04 3.66E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 8.92E+05 7.52E+05 3.27E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe133 1.27E+06 1.23E+06 1.07E+01 1.73E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135 5.33E+05 3.22E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
A-8

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

xe135m 1.29E+05 1.73E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y90 7.59E+04 7.53E+04 7.23E+04 7.10E+04 6.45E+04 5.71E+04 2.18E+04 6.55E+03 

y91 7.08E+05 7.04E+05 2.46E+05 9.45E+03 2.91E-04 1.19E-13 0.00E+00 0.00E+00 

y91m 3.10E+05 7.90E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 5.31E+05 2.42E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 6.39E+05 1.75E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr95 1.03E+06 1.02E+06 3.90E+05 1.99E+04 2.72E-03 7.15E-12 0.00E+00 0.00E+00 

zr97 8.71E+05 3.97E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 4.73E+07 3.53E+07 5.01E+06 1.94E+06 5.37E+05 3.77E+05 1.24E+05 3.96E+04 

Subtotal 92.4% 94.1% 96.2% 92.3% 90.1% 95.5% 100.0% 99.7% 
A-9

Table A.10. Nuclide activities (Ci/MTU) for BWR-3 (44 GWd/MTU)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

am241 2.10E+02 2.11E+02 2.62E+02 4.15E+02 1.14E+03 1.86E+03 3.93E+03 3.96E+03 

ba137m 1.29E+05 1.29E+05 1.28E+05 1.26E+05 1.15E+05 1.03E+05 4.08E+04 1.29E+04 

ba139 1.07E+05 7.89E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.10E+06 1.05E+06 8.33E+03 2.69E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce141 1.04E+06 1.03E+06 1.54E+05 4.38E+02 1.32E-11 1.67E-28 0.00E+00 0.00E+00 

ce143 8.71E+05 5.84E+05 2.02E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 8.64E+05 8.62E+05 6.94E+05 3.56E+05 1.02E+04 1.20E+02 4.51E-14 0.00E+00 

cm242 6.53E+04 6.53E+04 4.48E+04 1.39E+04 3.22E+01 4.23E+00 3.47E+00 2.71E+00 

cm244 4.48E+03 4.48E+03 4.43E+03 4.31E+03 3.70E+03 3.05E+03 6.61E+02 9.77E+01 

cs134 1.94E+05 1.94E+05 1.79E+05 1.39E+05 3.63E+04 6.79E+03 1.01E-02 5.27E-10 

cs136 4.35E+04 4.17E+04 3.84E+02 1.97E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 1.36E+05 1.36E+05 1.36E+05 1.33E+05 1.22E+05 1.08E+05 4.31E+04 1.36E+04 

i131 6.55E+05 6.18E+05 2.91E+02 1.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 9.19E+05 7.72E+05 3.36E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.15E+06 6.13E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 8.28E+04 3.27E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 7.49E+05 1.01E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 1.24E+04 1.24E+04 1.22E+04 1.16E+04 8.98E+03 6.51E+03 4.95E+02 1.98E+01 

kr85m 7.08E+04 3.74E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 1.95E+04 6.18E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 1.14E+05 1.10E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la140 1.16E+06 1.13E+06 9.59E+03 3.10E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 4.69E+05 1.63E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.15E+05 1.97E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo99 1.14E+06 9.36E+05 1.68E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb95 1.04E+06 1.03E+06 6.50E+05 4.28E+04 5.98E-03 1.57E-11 0.00E+00 0.00E+00 

nb97 9.31E+05 3.98E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 8.28E+05 3.77E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd147 4.14E+05 3.94E+05 1.43E+03 4.13E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
A-10

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

np239 1.30E+07 1.03E+07 3.10E+01 3.10E+01 3.10E+01 3.09E+01 3.08E+01 3.07E+01 

pr143 9.58E+05 9.49E+05 1.08E+04 8.54E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 8.64E+05 8.62E+05 6.95E+05 3.56E+05 1.02E+04 1.20E+02 4.51E-14 0.00E+00 

pr144m 8.25E+03 8.23E+03 6.63E+03 3.40E+03 9.74E+01 1.15E+00 4.30E-16 0.00E+00 

pu238 3.69E+03 3.69E+03 3.80E+03 3.94E+03 3.88E+03 3.73E+03 2.72E+03 1.84E+03 

pu239 3.01E+02 3.02E+02 3.05E+02 3.05E+02 3.05E+02 3.05E+02 3.04E+02 3.04E+02 

pu240 6.11E+02 6.11E+02 6.11E+02 6.11E+02 6.13E+02 6.14E+02 6.18E+02 6.17E+02 

pu241 1.31E+05 1.31E+05 1.30E+05 1.25E+05 1.03E+05 8.07E+04 1.16E+04 1.03E+03 

rb86 1.75E+03 1.70E+03 6.20E+01 2.23E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.27E+05 1.23E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103m 1.09E+06 1.07E+06 2.22E+05 1.73E+03 1.09E-08 1.10E-22 0.00E+00 0.00E+00 

rh105 7.20E+05 5.31E+05 3.49E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 4.85E+05 4.84E+05 4.10E+05 2.46E+05 1.62E+04 5.38E+02 8.11E-10 1.36E-24 

ru103 1.10E+06 1.08E+06 2.25E+05 1.75E+03 1.11E-08 1.11E-22 0.00E+00 0.00E+00 

ru105 3.82E+05 1.96E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 4.85E+05 4.84E+05 4.10E+05 2.46E+05 1.62E+04 5.38E+02 8.11E-10 1.36E-24 

sr89 5.32E+05 5.27E+05 1.55E+05 3.57E+03 7.16E-06 9.61E-17 0.00E+00 0.00E+00 

sr90 9.68E+04 9.68E+04 9.62E+04 9.45E+04 8.58E+04 7.61E+04 2.91E+04 8.73E+03 

sr91 4.82E+05 1.23E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 2.12E+05 1.64E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99m 1.05E+06 8.99E+05 1.62E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te127 5.99E+04 5.54E+04 2.79E+03 4.86E+02 4.52E-02 4.12E-07 0.00E+00 0.00E+00 

te127m 4.66E+03 4.69E+03 2.85E+03 4.96E+02 4.61E-02 4.20E-07 0.00E+00 0.00E+00 

te129 1.21E+05 2.50E+04 3.16E+03 1.09E+01 9.01E-13 0.00E+00 0.00E+00 0.00E+00 

te129m 3.18E+04 3.14E+04 5.00E+03 1.72E+01 1.43E-12 6.37E-29 0.00E+00 0.00E+00 

te131 3.16E+04 2.07E+04 9.48E-16 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 1.17E+05 7.88E+04 3.61E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 8.89E+05 7.49E+05 3.26E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe133 1.27E+06 1.23E+06 1.07E+01 1.74E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135 5.54E+05 3.27E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
A-11

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

xe135m 1.29E+05 1.73E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y90 1.01E+05 1.00E+05 9.63E+04 9.45E+04 8.59E+04 7.61E+04 2.91E+04 8.73E+03 

y91 7.06E+05 7.02E+05 2.45E+05 9.42E+03 2.90E-04 1.18E-13 0.00E+00 0.00E+00 

y91m 3.10E+05 7.91E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 5.31E+05 2.42E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 6.38E+05 1.75E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr95 1.03E+06 1.02E+06 3.89E+05 1.98E+04 2.71E-03 7.14E-12 0.00E+00 0.00E+00 

zr97 8.70E+05 3.96E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 4.74E+07 3.54E+07 5.35E+06 2.20E+06 6.80E+05 4.88E+05 1.63E+05 5.21E+04 

Subtotal 91.8% 93.5% 95.9% 92.3% 91.0% 95.9% 99.4% 99.6% 
A-12

Table A.11. Nuclide activities (Ci/MTU) for BWR-Ext (72 GWd/MTU)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

am241 2.88E+02 2.89E+02 3.52E+02 5.42E+02 1.44E+03 2.33E+03 4.91E+03 4.95E+03 

ba137m 2.03E+05 2.03E+05 2.02E+05 1.99E+05 1.81E+05 1.62E+05 6.43E+04 2.03E+04 

ba139 1.04E+05 7.67E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.06E+06 1.02E+06 8.04E+03 2.60E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce141 1.01E+06 9.91E+05 1.49E+05 4.22E+02 1.28E-11 1.61E-28 0.00E+00 0.00E+00 

ce143 8.22E+05 5.52E+05 1.90E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 8.23E+05 8.21E+05 6.61E+05 3.39E+05 9.71E+03 1.15E+02 4.29E-14 0.00E+00 

cm242 1.13E+05 1.13E+05 7.75E+04 2.41E+04 5.41E+01 5.70E+00 4.67E+00 3.65E+00 

cm244 2.16E+04 2.16E+04 2.14E+04 2.08E+04 1.78E+04 1.47E+04 3.19E+03 4.71E+02 

cs134 3.74E+05 3.74E+05 3.45E+05 2.68E+05 7.00E+04 1.31E+04 1.95E-02 1.02E-09 

cs136 7.86E+04 7.54E+04 6.94E+02 3.55E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 2.15E+05 2.15E+05 2.14E+05 2.10E+05 1.91E+05 1.71E+05 6.79E+04 2.15E+04 

i131 6.62E+05 6.25E+05 2.94E+02 1.42E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 9.20E+05 7.72E+05 3.36E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.14E+06 6.04E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 7.95E+04 3.13E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 7.44E+05 1.00E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 1.70E+04 1.70E+04 1.67E+04 1.59E+04 1.23E+04 8.93E+03 6.79E+02 2.71E+01 

kr85m 6.00E+04 3.17E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 1.61E+04 5.10E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 9.29E+04 8.98E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la140 1.15E+06 1.12E+06 9.26E+03 2.99E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 4.52E+05 1.57E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.10E+05 1.88E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo99 1.13E+06 9.26E+05 1.66E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb95 9.55E+05 9.55E+05 6.00E+05 3.95E+04 5.53E-03 1.45E-11 0.00E+00 0.00E+00 

nb97 8.98E+05 3.84E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 7.98E+05 3.64E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd147 4.10E+05 3.90E+05 1.42E+03 4.09E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
A-13

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

np239 1.44E+07 1.14E+07 8.77E+01 8.77E+01 8.76E+01 8.76E+01 8.73E+01 8.69E+01 

pr143 9.03E+05 8.94E+05 1.02E+04 8.05E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 8.23E+05 8.21E+05 6.62E+05 3.39E+05 9.71E+03 1.15E+02 4.29E-14 0.00E+00 

pr144m 7.86E+03 7.84E+03 6.32E+03 3.24E+03 9.27E+01 1.09E+00 4.10E-16 0.00E+00 

pu238 9.23E+03 9.24E+03 9.43E+03 9.64E+03 9.46E+03 9.10E+03 6.63E+03 4.47E+03 

pu239 3.02E+02 3.03E+02 3.06E+02 3.06E+02 3.06E+02 3.06E+02 3.06E+02 3.06E+02 

pu240 7.82E+02 7.82E+02 7.83E+02 7.84E+02 7.92E+02 8.00E+02 8.28E+02 8.32E+02 

pu241 1.63E+05 1.63E+05 1.61E+05 1.55E+05 1.28E+05 1.00E+05 1.44E+04 1.28E+03 

rb86 3.14E+03 3.05E+03 1.11E+02 4.01E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.04E+05 1.00E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103m 1.19E+06 1.17E+06 2.43E+05 1.89E+03 1.19E-08 1.20E-22 0.00E+00 0.00E+00 

rh105 8.25E+05 6.09E+05 4.00E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 6.42E+05 6.41E+05 5.43E+05 3.25E+05 2.14E+04 7.11E+02 1.07E-09 1.79E-24 

ru103 1.20E+06 1.18E+06 2.45E+05 1.91E+03 1.21E-08 1.21E-22 0.00E+00 0.00E+00 

ru105 4.42E+05 2.27E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 6.42E+05 6.41E+05 5.43E+05 3.25E+05 2.14E+04 7.11E+02 1.07E-09 1.79E-24 

sr89 4.31E+05 4.27E+05 1.26E+05 2.89E+03 5.80E-06 7.78E-17 0.00E+00 0.00E+00 

sr90 1.41E+05 1.41E+05 1.40E+05 1.38E+05 1.25E+05 1.11E+05 4.23E+04 1.27E+04 

sr91 4.06E+05 1.03E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 1.84E+05 1.42E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99m 1.04E+06 8.90E+05 1.61E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te127 6.42E+04 5.93E+04 2.81E+03 4.89E+02 4.54E-02 4.14E-07 0.00E+00 0.00E+00 

te127m 4.66E+03 4.69E+03 2.87E+03 4.99E+02 4.64E-02 4.23E-07 0.00E+00 0.00E+00 

te129 1.29E+05 2.67E+04 3.37E+03 1.16E+01 9.61E-13 0.00E+00 0.00E+00 0.00E+00 

te129m 3.39E+04 3.35E+04 5.34E+03 1.83E+01 1.52E-12 6.79E-29 0.00E+00 0.00E+00 

te131 3.30E+04 2.16E+04 9.92E-16 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 1.23E+05 8.25E+04 3.78E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 8.89E+05 7.49E+05 3.26E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe133 1.26E+06 1.22E+06 1.06E+01 1.72E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135 5.28E+05 3.19E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
A-14

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

xe135m 1.28E+05 1.72E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y90 1.48E+05 1.47E+05 1.40E+05 1.38E+05 1.25E+05 1.11E+05 4.23E+04 1.27E+04 

y91 5.91E+05 5.88E+05 2.05E+05 7.89E+03 2.43E-04 9.90E-14 0.00E+00 0.00E+00 

y91m 2.61E+05 6.65E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 4.60E+05 2.10E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 5.71E+05 1.56E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr95 9.50E+05 9.42E+05 3.60E+05 1.83E+04 2.51E-03 6.60E-12 0.00E+00 0.00E+00 

zr97 8.39E+05 3.82E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 5.02E+07 3.78E+07 5.95E+06 2.76E+06 9.94E+05 7.29E+05 2.49E+05 8.00E+04 

Subtotal 89.6% 91.5% 96.0% 93.5% 93.1% 96.7% 99.6% 99.5% 
A-15

Table A.12. Nuclide mass (gram/MTU) for BWR-1 (22 GWd/MTU)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years

100 

years

ag109 5.23E+01 5.24E+01 5.24E+01 5.24E+01 5.24E+01 5.24E+01 5.24E+01 5.24E+01 

am241 2.46E+01 2.47E+01 3.39E+01 6.17E+01 1.93E+02 3.23E+02 7.01E+02 7.07E+02 

am242 4.53E-02 1.99E-02 2.62E-06 2.61E-06 2.56E-06 2.49E-06 2.05E-06 1.60E-06 

am242m 2.03E-01 2.03E-01 2.03E-01 2.02E-01 1.98E-01 1.93E-01 1.59E-01 1.24E-01 

am243 3.90E+01 3.90E+01 3.90E+01 3.90E+01 3.90E+01 3.90E+01 3.88E+01 3.87E+01 

ba137 2.61E+01 2.61E+01 3.07E+01 4.45E+01 1.14E+02 1.92E+02 5.79E+02 7.54E+02 

ba137m 1.24E-04 1.24E-04 1.23E-04 1.21E-04 1.10E-04 9.81E-05 3.91E-05 1.24E-05 

ba138 8.68E+02 8.68E+02 8.68E+02 8.68E+02 8.68E+02 8.68E+02 8.68E+02 8.68E+02 

ba139 6.64E-03 4.89E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.52E+01 1.45E+01 1.15E-01 3.72E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce140 8.03E+02 8.03E+02 8.20E+02 8.20E+02 8.20E+02 8.20E+02 8.20E+02 8.20E+02 

ce141 3.71E+01 3.66E+01 5.48E+00 1.56E-02 4.70E-16 5.92E-33 0.00E+00 0.00E+00 

ce142 7.51E+02 7.51E+02 7.51E+02 7.51E+02 7.51E+02 7.51E+02 7.51E+02 7.51E+02 

ce143 1.34E+00 8.97E-01 3.09E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 2.45E+02 2.45E+02 1.97E+02 1.01E+02 2.90E+00 3.42E-02 1.28E-17 0.00E+00 

cm242 6.93E+00 6.93E+00 4.75E+00 1.48E+00 3.48E-03 5.05E-04 4.14E-04 3.24E-04 

cm243 1.04E-01 1.04E-01 1.03E-01 1.01E-01 9.22E-02 8.19E-02 3.16E-02 9.61E-03 

cm244 7.65E+00 7.65E+00 7.58E+00 7.36E+00 6.32E+00 5.22E+00 1.13E+00 1.67E-01 

cm245 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2.55E-01 2.54E-01 2.54E-01 2.53E-01 

cs133 7.88E+02 7.88E+02 7.95E+02 7.95E+02 7.95E+02 7.95E+02 7.95E+02 7.95E+02 

cs134 5.72E+01 5.72E+01 5.27E+01 4.09E+01 1.07E+01 2.00E+00 2.98E-06 1.55E-13 

cs136 2.96E-01 2.84E-01 2.61E-03 1.34E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 8.08E+02 8.08E+02 8.04E+02 7.90E+02 7.21E+02 6.42E+02 2.56E+02 8.08E+01 

eu151 8.36E-03 8.48E-03 2.23E-02 6.47E-02 2.86E-01 5.53E-01 2.36E+00 3.95E+00 

eu153 7.23E+01 7.24E+01 7.28E+01 7.28E+01 7.28E+01 7.28E+01 7.28E+01 7.28E+01 

eu154 1.15E+01 1.15E+01 1.13E+01 1.06E+01 7.71E+00 5.15E+00 2.06E-01 3.67E-03 

eu155 4.71E+00 4.71E+00 4.54E+00 4.07E+00 2.27E+00 1.10E+00 3.22E-03 2.21E-06 

gd155 3.37E-02 3.52E-02 2.00E-01 6.72E-01 2.47E+00 3.65E+00 4.74E+00 4.74E+00 

i131 5.28E+00 4.98E+00 2.35E-03 1.14E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
A-16

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years

100 

years

i132 8.91E-02 7.49E-02 3.26E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.03E+00 5.45E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 3.13E-03 1.24E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 2.13E-01 2.86E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 1.73E+01 1.73E+01 1.70E+01 1.62E+01 1.25E+01 9.08E+00 6.91E-01 2.76E-02 

kr85m 9.07E-03 4.79E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 7.33E-04 2.32E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 9.67E-03 9.35E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la139 8.15E+02 8.15E+02 8.15E+02 8.15E+02 8.15E+02 8.15E+02 8.15E+02 8.15E+02 

la140 2.07E+00 2.04E+00 1.75E-02 5.63E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 8.40E-02 2.91E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 8.07E-03 1.38E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo100 6.25E+02 6.25E+02 6.25E+02 6.25E+02 6.25E+02 6.25E+02 6.25E+02 6.25E+02 

mo95 4.41E+02 4.42E+02 4.82E+02 5.15E+02 5.17E+02 5.17E+02 5.17E+02 5.17E+02 

mo97 5.39E+02 5.39E+02 5.39E+02 5.39E+02 5.39E+02 5.39E+02 5.39E+02 5.39E+02 

mo98 5.51E+02 5.51E+02 5.51E+02 5.51E+02 5.51E+02 5.51E+02 5.51E+02 5.51E+02 

mo99 2.39E+00 1.96E+00 3.51E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb93m 2.97E-04 2.97E-04 3.45E-04 4.91E-04 1.19E-03 1.91E-03 4.38E-03 4.86E-03 

nb95 2.65E+01 2.65E+01 1.68E+01 1.11E+00 1.55E-07 4.08E-16 0.00E+00 0.00E+00 

nb97 3.51E-02 1.50E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 4.24E-04 1.93E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd143 5.38E+02 5.39E+02 5.54E+02 5.54E+02 5.54E+02 5.54E+02 5.54E+02 5.54E+02 

nd144 6.16E+02 6.16E+02 6.64E+02 7.60E+02 8.58E+02 8.61E+02 8.61E+02 8.61E+02 

nd145 4.63E+02 4.63E+02 4.63E+02 4.63E+02 4.63E+02 4.63E+02 4.63E+02 4.63E+02 

nd147 5.11E+00 4.86E+00 1.76E-02 5.09E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd148 2.48E+02 2.48E+02 2.48E+02 2.48E+02 2.48E+02 2.48E+02 2.48E+02 2.48E+02 

np237 2.11E+02 2.12E+02 2.16E+02 2.16E+02 2.17E+02 2.19E+02 2.55E+02 3.11E+02 

np239 5.85E+01 4.64E+01 3.36E-05 3.36E-05 3.36E-05 3.36E-05 3.34E-05 3.33E-05 

pm147 1.47E+02 1.47E+02 1.42E+02 1.17E+02 4.06E+01 1.08E+01 2.81E-04 5.18E-10 

pr141 7.13E+02 7.14E+02 7.45E+02 7.50E+02 7.50E+02 7.50E+02 7.50E+02 7.50E+02 
A-17

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years

100 

years

pr143 1.45E+01 1.44E+01 1.63E-01 1.29E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.03E-02 1.03E-02 8.31E-03 4.26E-03 1.22E-04 1.44E-06 5.39E-22 0.00E+00 

pr144m 4.11E-05 4.10E-05 3.31E-05 1.69E-05 4.85E-07 5.72E-09 2.15E-24 0.00E+00 

pu238 5.28E+01 5.29E+01 5.53E+01 5.82E+01 5.78E+01 5.56E+01 4.06E+01 2.73E+01 

pu239 4.12E+03 4.13E+03 4.17E+03 4.17E+03 4.17E+03 4.17E+03 4.17E+03 4.16E+03 

pu240 1.84E+03 1.84E+03 1.84E+03 1.84E+03 1.84E+03 1.84E+03 1.83E+03 1.82E+03 

pu241 7.86E+02 7.86E+02 7.76E+02 7.49E+02 6.17E+02 4.84E+02 6.96E+01 6.17E+00 

pu242 2.74E+02 2.74E+02 2.74E+02 2.74E+02 2.74E+02 2.74E+02 2.74E+02 2.74E+02 

rb86 1.04E-02 1.01E-02 3.69E-04 1.33E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.13E-03 1.09E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103 3.19E+02 3.19E+02 3.45E+02 3.51E+02 3.51E+02 3.51E+02 3.51E+02 3.51E+02 

rh103m 3.21E-02 3.17E-02 6.58E-03 5.11E-05 3.24E-16 3.25E-30 0.00E+00 0.00E+00 

rh105 8.00E-01 5.91E-01 3.88E-19 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 1.00E-04 9.98E-05 8.46E-05 5.06E-05 3.33E-06 1.11E-07 1.67E-19 2.79E-34 

ru101 5.28E+02 5.28E+02 5.28E+02 5.28E+02 5.28E+02 5.28E+02 5.28E+02 5.28E+02 

ru103 3.27E+01 3.22E+01 6.70E+00 5.21E-02 3.30E-13 3.31E-27 0.00E+00 0.00E+00 

ru105 5.37E-02 2.76E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 1.07E+02 1.07E+02 9.03E+01 5.41E+01 3.56E+00 1.18E-01 1.79E-13 2.98E-28 

sb125 6.03E+00 6.03E+00 5.73E+00 4.74E+00 1.74E+00 4.95E-01 2.15E-05 7.58E-11 

sm147 5.76E+01 5.77E+01 6.71E+01 9.28E+01 1.69E+02 1.99E+02 2.10E+02 2.10E+02 

sm149 1.43E+00 1.60E+00 2.21E+00 2.21E+00 2.21E+00 2.21E+00 2.21E+00 2.21E+00 

sm150 1.87E+02 1.87E+02 1.87E+02 1.87E+02 1.87E+02 1.87E+02 1.87E+02 1.87E+02 

sm151 7.19E+00 7.25E+00 7.34E+00 7.29E+00 7.07E+00 6.81E+00 5.00E+00 3.41E+00 

sm152 8.57E+01 8.57E+01 8.57E+01 8.57E+01 8.57E+01 8.57E+01 8.57E+01 8.57E+01 

sr89 1.96E+01 1.94E+01 5.72E+00 1.32E-01 2.64E-10 3.54E-21 0.00E+00 0.00E+00 

sr90 3.64E+02 3.63E+02 3.61E+02 3.55E+02 3.22E+02 2.86E+02 1.09E+02 3.28E+01 

sr91 1.43E-01 3.63E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 1.77E-02 1.37E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99 5.54E+02 5.55E+02 5.57E+02 5.57E+02 5.57E+02 5.57E+02 5.57E+02 5.56E+02 

tc99m 2.00E-01 1.71E-01 3.09E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
A-18

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years

100 

years

te125m 7.22E-02 7.22E-02 7.55E-02 6.60E-02 2.42E-02 6.90E-03 3.00E-07 1.06E-12 

te127 2.23E-02 2.06E-02 9.77E-04 1.70E-04 1.58E-08 1.44E-13 0.00E+00 0.00E+00 

te127m 4.53E-01 4.56E-01 2.79E-01 4.85E-02 4.51E-06 4.11E-11 0.00E+00 0.00E+00 

te129 5.70E-03 1.18E-03 1.48E-04 5.10E-07 4.24E-20 0.00E+00 0.00E+00 0.00E+00 

te129m 1.04E+00 1.03E+00 1.64E-01 5.62E-04 4.67E-17 2.08E-33 0.00E+00 0.00E+00 

te131 5.53E-04 3.62E-04 1.66E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 1.64E-01 1.10E-01 5.05E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 2.89E+00 2.44E+00 1.06E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

u234 1.41E+02 1.41E+02 1.41E+02 1.41E+02 1.43E+02 1.45E+02 1.60E+02 1.73E+02 

u235 7.21E+03 7.21E+03 7.21E+03 7.21E+03 7.21E+03 7.21E+03 7.22E+03 7.22E+03 

u236 2.74E+03 2.74E+03 2.74E+03 2.74E+03 2.74E+03 2.75E+03 2.75E+03 2.76E+03 

u238 9.60E+05 9.60E+05 9.60E+05 9.60E+05 9.60E+05 9.60E+05 9.60E+05 9.60E+05 

xe132 6.92E+02 6.93E+02 6.95E+02 6.95E+02 6.95E+02 6.95E+02 6.95E+02 6.95E+02 

xe133 6.78E+00 6.57E+00 5.72E-05 9.29E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe134 1.01E+03 1.01E+03 1.01E+03 1.01E+03 1.01E+03 1.01E+03 1.01E+03 1.01E+03 

xe135 2.06E-01 1.26E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 1.42E-03 1.91E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe136 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 

y90 9.62E-02 9.54E-02 9.17E-02 9.00E-02 8.18E-02 7.25E-02 2.77E-02 8.31E-03 

y91 3.04E+01 3.02E+01 1.05E+01 4.05E-01 1.25E-08 5.09E-18 0.00E+00 0.00E+00 

y91m 7.88E-03 2.01E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 5.78E-02 2.64E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 2.01E-01 5.50E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr93 4.79E+02 4.79E+02 4.79E+02 4.79E+02 4.79E+02 4.79E+02 4.79E+02 4.79E+02 

zr95 4.88E+01 4.84E+01 1.85E+01 9.41E-01 1.29E-07 3.39E-16 0.00E+00 0.00E+00 

zr97 4.57E-01 2.08E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 

Subtotal 99.4% 99.4% 99.3% 99.3% 99.3% 99.3% 99.3% 99.3% 
A-19

Table A.13. Nuclide mass (gram/MTU) for BWR-2 (33 GWd/MTU)

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

ag109 7.89E+01 7.90E+01 7.90E+01 7.90E+01 7.90E+01 7.90E+01 7.90E+01 7.90E+01 

am241 4.29E+01 4.31E+01 5.55E+01 9.32E+01 2.71E+02 4.48E+02 9.59E+02 9.67E+02 

am242 7.52E-02 3.31E-02 4.62E-06 4.60E-06 4.52E-06 4.41E-06 3.62E-06 2.83E-06 

am242m 3.59E-01 3.59E-01 3.58E-01 3.57E-01 3.50E-01 3.41E-01 2.81E-01 2.19E-01 

am243 9.83E+01 9.83E+01 9.83E+01 9.83E+01 9.83E+01 9.83E+01 9.79E+01 9.74E+01 

ba137 5.62E+01 5.62E+01 6.29E+01 8.34E+01 1.86E+02 3.02E+02 8.74E+02 1.13E+03 

ba137m 1.83E-04 1.83E-04 1.82E-04 1.79E-04 1.63E-04 1.45E-04 5.78E-05 1.83E-05 

ba138 1.30E+03 1.30E+03 1.30E+03 1.30E+03 1.30E+03 1.30E+03 1.30E+03 1.30E+03 

ba139 6.58E-03 4.84E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.50E+01 1.44E+01 1.14E-01 3.68E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce140 1.21E+03 1.21E+03 1.23E+03 1.23E+03 1.23E+03 1.23E+03 1.23E+03 1.23E+03 

ce141 3.67E+01 3.61E+01 5.42E+00 1.54E-02 4.65E-16 5.85E-33 0.00E+00 0.00E+00 

ce142 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 

ce143 1.31E+00 8.80E-01 3.03E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 2.63E+02 2.62E+02 2.11E+02 1.08E+02 3.10E+00 3.66E-02 1.37E-17 0.00E+00 

cm242 1.39E+01 1.39E+01 9.51E+00 2.95E+00 6.84E-03 8.92E-04 7.31E-04 5.72E-04 

cm243 2.86E-01 2.86E-01 2.85E-01 2.80E-01 2.54E-01 2.26E-01 8.71E-02 2.65E-02 

cm244 2.83E+01 2.83E+01 2.80E+01 2.72E+01 2.34E+01 1.93E+01 4.18E+00 6.17E-01 

cm245 1.21E+00 1.21E+00 1.21E+00 1.21E+00 1.21E+00 1.21E+00 1.21E+00 1.20E+00 

cs133 1.14E+03 1.14E+03 1.14E+03 1.14E+03 1.14E+03 1.14E+03 1.14E+03 1.14E+03 

cs134 1.05E+02 1.05E+02 9.63E+01 7.48E+01 1.96E+01 3.66E+00 5.45E-06 2.84E-13 

cs136 4.38E-01 4.20E-01 3.87E-03 1.98E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 1.20E+03 1.20E+03 1.19E+03 1.17E+03 1.07E+03 9.50E+02 3.78E+02 1.20E+02 

eu151 1.11E-02 1.12E-02 2.84E-02 8.12E-02 3.57E-01 6.90E-01 2.94E+00 4.93E+00 

eu153 1.15E+02 1.15E+02 1.15E+02 1.15E+02 1.15E+02 1.15E+02 1.15E+02 1.15E+02 

eu154 2.07E+01 2.07E+01 2.03E+01 1.91E+01 1.38E+01 9.25E+00 3.69E-01 6.58E-03 

eu155 7.85E+00 7.85E+00 7.57E+00 6.78E+00 3.79E+00 1.83E+00 5.37E-03 3.68E-06 

gd155 6.35E-02 6.60E-02 3.40E-01 1.13E+00 4.12E+00 6.08E+00 7.91E+00 7.91E+00 

i131 5.29E+00 4.99E+00 2.35E-03 1.14E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 8.91E-02 7.49E-02 3.25E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
A-20

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

i133 1.02E+00 5.42E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 3.09E-03 1.22E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 2.12E-01 2.86E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 2.44E+01 2.44E+01 2.40E+01 2.29E+01 1.77E+01 1.28E+01 9.76E-01 3.90E-02 

kr85m 8.59E-03 4.54E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 6.89E-04 2.18E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 9.07E-03 8.77E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la139 1.22E+03 1.22E+03 1.22E+03 1.22E+03 1.22E+03 1.22E+03 1.22E+03 1.22E+03 

la140 2.06E+00 2.03E+00 1.73E-02 5.57E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 8.29E-02 2.88E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 7.94E-03 1.35E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo100 9.36E+02 9.36E+02 9.36E+02 9.36E+02 9.36E+02 9.36E+02 9.36E+02 9.36E+02 

mo95 6.82E+02 6.82E+02 7.21E+02 7.54E+02 7.56E+02 7.56E+02 7.56E+02 7.56E+02 

mo97 8.03E+02 8.04E+02 8.04E+02 8.04E+02 8.04E+02 8.04E+02 8.04E+02 8.04E+02 

mo98 8.25E+02 8.25E+02 8.25E+02 8.25E+02 8.25E+02 8.25E+02 8.25E+02 8.25E+02 

mo99 2.38E+00 1.95E+00 3.50E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb93m 6.29E-04 6.29E-04 6.99E-04 9.08E-04 1.91E-03 2.95E-03 6.50E-03 7.19E-03 

nb95 2.63E+01 2.63E+01 1.66E+01 1.09E+00 1.52E-07 4.01E-16 0.00E+00 0.00E+00 

nb97 3.46E-02 1.48E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 4.18E-04 1.90E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd143 7.33E+02 7.34E+02 7.49E+02 7.49E+02 7.49E+02 7.49E+02 7.49E+02 7.49E+02 

nd144 1.10E+03 1.10E+03 1.15E+03 1.25E+03 1.36E+03 1.36E+03 1.36E+03 1.36E+03 

nd145 6.66E+02 6.66E+02 6.66E+02 6.66E+02 6.66E+02 6.66E+02 6.66E+02 6.66E+02 

nd147 5.10E+00 4.85E+00 1.76E-02 5.08E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd148 3.69E+02 3.69E+02 3.69E+02 3.69E+02 3.69E+02 3.69E+02 3.69E+02 3.69E+02 

np237 3.59E+02 3.59E+02 3.65E+02 3.65E+02 3.66E+02 3.69E+02 4.18E+02 4.96E+02 

np239 5.84E+01 4.63E+01 8.47E-05 8.47E-05 8.46E-05 8.46E-05 8.43E-05 8.39E-05 

pm147 1.73E+02 1.73E+02 1.67E+02 1.37E+02 4.75E+01 1.27E+01 3.29E-04 6.07E-10 

pr141 1.08E+03 1.08E+03 1.11E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 

pr143 1.42E+01 1.41E+01 1.60E-01 1.27E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.11E-02 1.11E-02 8.90E-03 4.56E-03 1.31E-04 1.54E-06 5.78E-22 0.00E+00 

pr144m 4.41E-05 4.40E-05 3.54E-05 1.81E-05 5.20E-07 6.13E-09 2.30E-24 0.00E+00 
A-21

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

pu238 1.23E+02 1.23E+02 1.28E+02 1.34E+02 1.32E+02 1.27E+02 9.27E+01 6.25E+01 

pu239 4.48E+03 4.50E+03 4.54E+03 4.54E+03 4.54E+03 4.54E+03 4.54E+03 4.53E+03 

pu240 2.37E+03 2.37E+03 2.37E+03 2.37E+03 2.37E+03 2.38E+03 2.38E+03 2.37E+03 

pu241 1.07E+03 1.07E+03 1.05E+03 1.02E+03 8.36E+02 6.56E+02 9.44E+01 8.36E+00 

pu242 5.08E+02 5.08E+02 5.08E+02 5.08E+02 5.08E+02 5.08E+02 5.08E+02 5.08E+02 

rb86 1.59E-02 1.55E-02 5.65E-04 2.03E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.06E-03 1.02E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103 4.45E+02 4.46E+02 4.72E+02 4.79E+02 4.79E+02 4.79E+02 4.79E+02 4.79E+02 

rh103m 3.33E-02 3.29E-02 6.82E-03 5.31E-05 3.36E-16 3.37E-30 0.00E+00 0.00E+00 

rh105 8.49E-01 6.26E-01 4.11E-19 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 1.27E-04 1.26E-04 1.07E-04 6.41E-05 4.22E-06 1.40E-07 2.12E-19 3.54E-34 

ru101 7.83E+02 7.83E+02 7.83E+02 7.83E+02 7.83E+02 7.83E+02 7.83E+02 7.83E+02 

ru103 3.39E+01 3.35E+01 6.95E+00 5.40E-02 3.42E-13 3.44E-27 0.00E+00 0.00E+00 

ru105 5.69E-02 2.92E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 1.35E+02 1.35E+02 1.14E+02 6.85E+01 4.50E+00 1.50E-01 2.26E-13 3.78E-28 

sb125 8.08E+00 8.08E+00 7.65E+00 6.33E+00 2.32E+00 6.61E-01 2.87E-05 1.01E-10 

sm147 9.94E+01 9.95E+01 1.11E+02 1.41E+02 2.30E+02 2.65E+02 2.77E+02 2.77E+02 

sm149 1.59E+00 1.77E+00 2.41E+00 2.41E+00 2.41E+00 2.41E+00 2.41E+00 2.41E+00 

sm150 2.81E+02 2.81E+02 2.81E+02 2.81E+02 2.81E+02 2.81E+02 2.81E+02 2.81E+02 

sm151 9.00E+00 9.06E+00 9.14E+00 9.09E+00 8.81E+00 8.48E+00 6.23E+00 4.24E+00 

sm152 1.13E+02 1.13E+02 1.13E+02 1.13E+02 1.13E+02 1.13E+02 1.13E+02 1.13E+02 

sr89 1.84E+01 1.82E+01 5.36E+00 1.23E-01 2.47E-10 3.32E-21 0.00E+00 0.00E+00 

sr90 5.26E+02 5.26E+02 5.23E+02 5.14E+02 4.67E+02 4.14E+02 1.58E+02 4.75E+01 

sr91 1.35E-01 3.43E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 1.69E-02 1.31E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99 8.09E+02 8.09E+02 8.11E+02 8.11E+02 8.11E+02 8.11E+02 8.11E+02 8.11E+02 

tc99m 1.99E-01 1.70E-01 3.08E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te125m 1.00E-01 1.00E-01 1.02E-01 8.82E-02 3.24E-02 9.22E-03 4.01E-07 1.41E-12 

te127 2.28E-02 2.11E-02 1.02E-03 1.78E-04 1.65E-08 1.51E-13 0.00E+00 0.00E+00 

te127m 4.75E-01 4.78E-01 2.92E-01 5.08E-02 4.72E-06 4.30E-11 0.00E+00 0.00E+00 

te129 5.81E-03 1.20E-03 1.52E-04 5.22E-07 4.33E-20 0.00E+00 0.00E+00 0.00E+00 

te129m 1.06E+00 1.05E+00 1.67E-01 5.75E-04 4.77E-17 2.13E-33 0.00E+00 0.00E+00 
A-22

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

te131 5.57E-04 3.65E-04 1.67E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 1.65E-01 1.11E-01 5.09E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 2.89E+00 2.43E+00 1.06E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

u234 1.57E+02 1.57E+02 1.58E+02 1.58E+02 1.63E+02 1.68E+02 2.01E+02 2.31E+02 

u235 6.53E+03 6.53E+03 6.53E+03 6.53E+03 6.53E+03 6.53E+03 6.54E+03 6.55E+03 

u236 3.95E+03 3.95E+03 3.95E+03 3.95E+03 3.95E+03 3.95E+03 3.96E+03 3.97E+03 

u238 9.46E+05 9.46E+05 9.46E+05 9.46E+05 9.46E+05 9.46E+05 9.46E+05 9.46E+05 

xe132 1.08E+03 1.08E+03 1.09E+03 1.09E+03 1.09E+03 1.09E+03 1.09E+03 1.09E+03 

xe133 6.76E+00 6.55E+00 5.70E-05 9.25E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe134 1.52E+03 1.52E+03 1.52E+03 1.52E+03 1.52E+03 1.52E+03 1.52E+03 1.52E+03 

xe135 2.10E-01 1.27E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 1.41E-03 1.90E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe136 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 

y90 1.40E-01 1.38E-01 1.33E-01 1.30E-01 1.18E-01 1.05E-01 4.01E-02 1.20E-02 

y91 2.89E+01 2.87E+01 1.00E+01 3.85E-01 1.19E-08 4.83E-18 0.00E+00 0.00E+00 

y91m 7.45E-03 1.90E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 5.52E-02 2.52E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 1.93E-01 5.29E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr93 7.08E+02 7.08E+02 7.08E+02 7.08E+02 7.08E+02 7.08E+02 7.08E+02 7.08E+02 

zr95 4.80E+01 4.76E+01 1.82E+01 9.25E-01 1.27E-07 3.33E-16 0.00E+00 0.00E+00 

zr97 4.51E-01 2.06E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 

Subtotal 99.0% 99.0% 99.0% 99.0% 99.0% 99.0% 98.9% 98.9% 
A-23

Table A.14. Nuclide mass (gram/MTU) for BWR-3 (44 GWd/MTU)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

ag109 9.84E+01 9.84E+01 9.84E+01 9.84E+01 9.84E+01 9.84E+01 9.84E+01 9.84E+01 

am241 6.13E+01 6.14E+01 7.62E+01 1.21E+02 3.31E+02 5.41E+02 1.15E+03 1.15E+03 

am242 9.79E-02 4.30E-02 6.62E-06 6.59E-06 6.46E-06 6.31E-06 5.18E-06 4.05E-06 

am242m 5.13E-01 5.13E-01 5.13E-01 5.11E-01 5.01E-01 4.89E-01 4.02E-01 3.14E-01 

am243 1.55E+02 1.55E+02 1.55E+02 1.55E+02 1.55E+02 1.55E+02 1.54E+02 1.54E+02 

ba137 9.71E+01 9.72E+01 1.06E+02 1.33E+02 2.68E+02 4.20E+02 1.17E+03 1.51E+03 

ba137m 2.40E-04 2.40E-04 2.39E-04 2.35E-04 2.14E-04 1.91E-04 7.59E-05 2.40E-05 

ba138 1.74E+03 1.74E+03 1.74E+03 1.74E+03 1.74E+03 1.74E+03 1.74E+03 1.74E+03 

ba139 6.59E-03 4.84E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.50E+01 1.44E+01 1.14E-01 3.67E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce140 1.63E+03 1.63E+03 1.65E+03 1.65E+03 1.65E+03 1.65E+03 1.65E+03 1.65E+03 

ce141 3.66E+01 3.61E+01 5.41E+00 1.54E-02 4.64E-16 5.84E-33 0.00E+00 0.00E+00 

ce142 1.50E+03 1.50E+03 1.50E+03 1.50E+03 1.50E+03 1.50E+03 1.50E+03 1.50E+03 

ce143 1.31E+00 8.80E-01 3.04E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 2.71E+02 2.71E+02 2.18E+02 1.12E+02 3.20E+00 3.78E-02 1.42E-17 0.00E+00 

cm242 1.97E+01 1.97E+01 1.35E+01 4.20E+00 9.73E-03 1.28E-03 1.05E-03 8.18E-04 

cm243 4.85E-01 4.85E-01 4.82E-01 4.74E-01 4.31E-01 3.82E-01 1.48E-01 4.49E-02 

cm244 5.53E+01 5.53E+01 5.48E+01 5.32E+01 4.57E+01 3.77E+01 8.17E+00 1.21E+00 

cm245 2.77E+00 2.77E+00 2.77E+00 2.77E+00 2.77E+00 2.77E+00 2.76E+00 2.75E+00 

cs133 1.47E+03 1.47E+03 1.48E+03 1.48E+03 1.48E+03 1.48E+03 1.48E+03 1.48E+03 

cs134 1.50E+02 1.50E+02 1.38E+02 1.08E+02 2.81E+01 5.25E+00 7.83E-06 4.08E-13 

cs136 5.96E-01 5.71E-01 5.26E-03 2.69E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 1.57E+03 1.57E+03 1.56E+03 1.54E+03 1.40E+03 1.25E+03 4.97E+02 1.57E+02 

eu151 1.53E-02 1.55E-02 3.66E-02 1.02E-01 4.41E-01 8.50E-01 3.62E+00 6.07E+00 

eu153 1.51E+02 1.51E+02 1.52E+02 1.52E+02 1.52E+02 1.52E+02 1.52E+02 1.52E+02 

eu154 2.96E+01 2.96E+01 2.91E+01 2.73E+01 1.98E+01 1.33E+01 5.29E-01 9.42E-03 

eu155 1.07E+01 1.07E+01 1.03E+01 9.23E+00 5.15E+00 2.49E+00 7.31E-03 5.00E-06 

gd155 1.03E-01 1.07E-01 4.79E-01 1.55E+00 5.63E+00 8.30E+00 1.08E+01 1.08E+01 

i131 5.27E+00 4.97E+00 2.34E-03 1.13E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 8.88E-02 7.46E-02 3.24E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
A-24

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

i133 1.02E+00 5.41E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 3.10E-03 1.22E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 2.12E-01 2.85E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 3.17E+01 3.17E+01 3.12E+01 2.97E+01 2.30E+01 1.66E+01 1.27E+00 5.06E-02 

kr85m 8.60E-03 4.54E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 6.89E-04 2.18E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 9.08E-03 8.78E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la139 1.62E+03 1.62E+03 1.62E+03 1.62E+03 1.62E+03 1.62E+03 1.62E+03 1.62E+03 

la140 2.08E+00 2.04E+00 1.73E-02 5.57E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 8.28E-02 2.87E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 7.93E-03 1.35E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo100 1.25E+03 1.25E+03 1.25E+03 1.25E+03 1.25E+03 1.25E+03 1.25E+03 1.25E+03 

mo95 9.27E+02 9.27E+02 9.66E+02 9.99E+02 1.00E+03 1.00E+03 1.00E+03 1.00E+03 

mo97 1.07E+03 1.07E+03 1.07E+03 1.07E+03 1.07E+03 1.07E+03 1.07E+03 1.07E+03 

mo98 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 

mo99 2.38E+00 1.95E+00 3.50E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb93m 1.09E-03 1.09E-03 1.18E-03 1.45E-03 2.77E-03 4.12E-03 8.76E-03 9.65E-03 

nb95 2.63E+01 2.63E+01 1.65E+01 1.09E+00 1.52E-07 4.01E-16 0.00E+00 0.00E+00 

nb97 3.46E-02 1.48E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 4.18E-04 1.90E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd143 9.38E+02 9.39E+02 9.54E+02 9.54E+02 9.54E+02 9.54E+02 9.54E+02 9.54E+02 

nd144 1.60E+03 1.60E+03 1.66E+03 1.76E+03 1.87E+03 1.87E+03 1.87E+03 1.87E+03 

nd145 8.71E+02 8.71E+02 8.71E+02 8.71E+02 8.71E+02 8.71E+02 8.71E+02 8.71E+02 

nd147 5.12E+00 4.87E+00 1.77E-02 5.10E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd148 4.91E+02 4.91E+02 4.91E+02 4.91E+02 4.91E+02 4.91E+02 4.91E+02 4.91E+02 

np237 5.28E+02 5.28E+02 5.35E+02 5.35E+02 5.36E+02 5.40E+02 5.99E+02 6.91E+02 

np239 5.59E+01 4.43E+01 1.34E-04 1.34E-04 1.33E-04 1.33E-04 1.33E-04 1.32E-04 

pm147 1.93E+02 1.93E+02 1.86E+02 1.52E+02 5.30E+01 1.41E+01 3.66E-04 6.76E-10 

pr141 1.45E+03 1.45E+03 1.48E+03 1.49E+03 1.49E+03 1.49E+03 1.49E+03 1.49E+03 

pr143 1.42E+01 1.41E+01 1.60E-01 1.27E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.14E-02 1.14E-02 9.19E-03 4.71E-03 1.35E-04 1.59E-06 5.96E-22 0.00E+00 

pr144m 4.55E-05 4.54E-05 3.66E-05 1.87E-05 5.37E-07 6.33E-09 2.37E-24 0.00E+00 
A-25

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

pu238 2.15E+02 2.15E+02 2.22E+02 2.30E+02 2.27E+02 2.18E+02 1.59E+02 1.07E+02 

pu239 4.85E+03 4.86E+03 4.91E+03 4.91E+03 4.91E+03 4.91E+03 4.90E+03 4.89E+03 

pu240 2.69E+03 2.69E+03 2.69E+03 2.69E+03 2.70E+03 2.71E+03 2.72E+03 2.72E+03 

pu241 1.26E+03 1.26E+03 1.25E+03 1.20E+03 9.90E+02 7.77E+02 1.12E+02 9.91E+00 

pu242 6.80E+02 6.80E+02 6.80E+02 6.80E+02 6.80E+02 6.80E+02 6.80E+02 6.80E+02 

rb86 2.15E-02 2.09E-02 7.61E-04 2.74E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.06E-03 1.02E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103 5.49E+02 5.50E+02 5.76E+02 5.83E+02 5.83E+02 5.83E+02 5.83E+02 5.83E+02 

rh103m 3.33E-02 3.29E-02 6.83E-03 5.31E-05 3.36E-16 3.37E-30 0.00E+00 0.00E+00 

rh105 8.52E-01 6.28E-01 4.13E-19 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 1.37E-04 1.37E-04 1.16E-04 6.94E-05 4.56E-06 1.52E-07 2.29E-19 3.83E-34 

ru101 1.03E+03 1.03E+03 1.03E+03 1.03E+03 1.03E+03 1.03E+03 1.03E+03 1.03E+03 

ru103 3.39E+01 3.35E+01 6.95E+00 5.40E-02 3.42E-13 3.44E-27 0.00E+00 0.00E+00 

ru105 5.67E-02 2.92E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 1.46E+02 1.46E+02 1.24E+02 7.41E+01 4.87E+00 1.62E-01 2.45E-13 4.09E-28 

sb125 9.39E+00 9.39E+00 8.89E+00 7.36E+00 2.69E+00 7.68E-01 3.34E-05 1.18E-10 

sm147 1.45E+02 1.45E+02 1.58E+02 1.91E+02 2.90E+02 3.29E+02 3.43E+02 3.43E+02 

sm149 1.82E+00 2.01E+00 2.66E+00 2.66E+00 2.66E+00 2.66E+00 2.66E+00 2.66E+00 

sm150 3.69E+02 3.69E+02 3.69E+02 3.69E+02 3.69E+02 3.69E+02 3.69E+02 3.69E+02 

sm151 1.11E+01 1.12E+01 1.13E+01 1.12E+01 1.09E+01 1.04E+01 7.67E+00 5.22E+00 

sm152 1.35E+02 1.35E+02 1.35E+02 1.35E+02 1.35E+02 1.35E+02 1.35E+02 1.35E+02 

sr89 1.83E+01 1.81E+01 5.35E+00 1.23E-01 2.47E-10 3.31E-21 0.00E+00 0.00E+00 

sr90 7.01E+02 7.01E+02 6.97E+02 6.85E+02 6.22E+02 5.51E+02 2.11E+02 6.32E+01 

sr91 1.35E-01 3.43E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 1.69E-02 1.30E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99 1.06E+03 1.06E+03 1.06E+03 1.06E+03 1.06E+03 1.06E+03 1.06E+03 1.06E+03 

tc99m 2.00E-01 1.71E-01 3.08E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te125m 1.19E-01 1.19E-01 1.19E-01 1.02E-01 3.76E-02 1.07E-02 4.65E-07 1.64E-12 

te127 2.27E-02 2.10E-02 1.06E-03 1.84E-04 1.71E-08 1.56E-13 0.00E+00 0.00E+00 

te127m 4.94E-01 4.97E-01 3.02E-01 5.26E-02 4.88E-06 4.45E-11 0.00E+00 0.00E+00 

te129 5.77E-03 1.19E-03 1.51E-04 5.18E-07 4.30E-20 0.00E+00 0.00E+00 0.00E+00 

te129m 1.06E+00 1.04E+00 1.66E-01 5.71E-04 4.74E-17 2.11E-33 0.00E+00 0.00E+00 
A-26

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

te131 5.50E-04 3.60E-04 1.65E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 1.63E-01 1.10E-01 5.02E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 2.88E+00 2.43E+00 1.05E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

u234 1.91E+02 1.91E+02 1.92E+02 1.93E+02 2.00E+02 2.09E+02 2.67E+02 3.18E+02 

u235 7.42E+03 7.42E+03 7.42E+03 7.42E+03 7.42E+03 7.42E+03 7.42E+03 7.43E+03 

u236 5.49E+03 5.49E+03 5.49E+03 5.49E+03 5.49E+03 5.49E+03 5.50E+03 5.52E+03 

u238 9.31E+05 9.31E+05 9.31E+05 9.31E+05 9.31E+05 9.31E+05 9.31E+05 9.31E+05 

xe132 1.48E+03 1.48E+03 1.48E+03 1.48E+03 1.48E+03 1.48E+03 1.48E+03 1.48E+03 

xe133 6.77E+00 6.55E+00 5.70E-05 9.26E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe134 2.02E+03 2.02E+03 2.02E+03 2.02E+03 2.02E+03 2.02E+03 2.02E+03 2.02E+03 

xe135 2.18E-01 1.29E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 1.41E-03 1.90E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe136 2.96E+03 2.96E+03 2.96E+03 2.96E+03 2.96E+03 2.96E+03 2.96E+03 2.96E+03 

y90 1.86E-01 1.84E-01 1.77E-01 1.74E-01 1.58E-01 1.40E-01 5.34E-02 1.60E-02 

y91 2.88E+01 2.86E+01 9.98E+00 3.84E-01 1.18E-08 4.82E-18 0.00E+00 0.00E+00 

y91m 7.45E-03 1.90E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 5.51E-02 2.52E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 1.93E-01 5.28E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr93 9.50E+02 9.50E+02 9.51E+02 9.51E+02 9.51E+02 9.51E+02 9.51E+02 9.51E+02 

zr95 4.79E+01 4.75E+01 1.81E+01 9.23E-01 1.26E-07 3.32E-16 0.00E+00 0.00E+00 

zr97 4.51E-01 2.05E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 

Subtotal 98.6% 98.6% 98.6% 98.6% 98.6% 98.6% 98.5% 98.5% 
A-27

Table A.15. Nuclide mass (gram/MTU) for BWR-Ext (72 GWd/MTU)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

ag109 1.69E+02 1.69E+02 1.69E+02 1.69E+02 1.69E+02 1.69E+02 1.69E+02 1.69E+02 

am241 8.40E+01 8.42E+01 1.03E+02 1.58E+02 4.20E+02 6.80E+02 1.43E+03 1.44E+03 

am242 1.47E-01 6.47E-02 8.91E-06 8.88E-06 8.71E-06 8.50E-06 6.98E-06 5.46E-06 

am242m 6.92E-01 6.92E-01 6.91E-01 6.88E-01 6.75E-01 6.58E-01 5.41E-01 4.23E-01 

am243 4.39E+02 4.39E+02 4.39E+02 4.39E+02 4.39E+02 4.39E+02 4.37E+02 4.35E+02 

ba137 2.47E+02 2.47E+02 2.61E+02 3.03E+02 5.16E+02 7.56E+02 1.94E+03 2.47E+03 

ba137m 3.78E-04 3.78E-04 3.76E-04 3.69E-04 3.37E-04 3.00E-04 1.20E-04 3.78E-05 

ba138 2.81E+03 2.81E+03 2.81E+03 2.81E+03 2.81E+03 2.81E+03 2.81E+03 2.81E+03 

ba139 6.40E-03 4.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.45E+01 1.39E+01 1.10E-01 3.55E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce140 2.67E+03 2.67E+03 2.69E+03 2.69E+03 2.69E+03 2.69E+03 2.69E+03 2.69E+03 

ce141 3.53E+01 3.48E+01 5.22E+00 1.48E-02 4.47E-16 5.63E-33 0.00E+00 0.00E+00 

ce142 2.40E+03 2.40E+03 2.40E+03 2.40E+03 2.40E+03 2.40E+03 2.40E+03 2.40E+03 

ce143 1.24E+00 8.31E-01 2.87E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 2.59E+02 2.58E+02 2.08E+02 1.06E+02 3.05E+00 3.60E-02 1.35E-17 0.00E+00 

cm242 3.41E+01 3.41E+01 2.34E+01 7.26E+00 1.63E-02 1.72E-03 1.41E-03 1.10E-03 

cm243 1.21E+00 1.21E+00 1.20E+00 1.18E+00 1.07E+00 9.51E-01 3.67E-01 1.12E-01 

cm244 2.67E+02 2.67E+02 2.64E+02 2.57E+02 2.20E+02 1.82E+02 3.94E+01 5.82E+00 

cm245 1.60E+01 1.60E+01 1.60E+01 1.60E+01 1.60E+01 1.60E+01 1.60E+01 1.59E+01 

cs133 2.15E+03 2.15E+03 2.16E+03 2.16E+03 2.16E+03 2.16E+03 2.16E+03 2.16E+03 

cs134 2.90E+02 2.89E+02 2.67E+02 2.07E+02 5.42E+01 1.01E+01 1.51E-05 7.86E-13 

cs136 1.08E+00 1.03E+00 9.51E-03 4.87E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 2.48E+03 2.47E+03 2.46E+03 2.42E+03 2.21E+03 1.97E+03 7.82E+02 2.47E+02 

eu151 1.63E-02 1.65E-02 4.22E-02 1.21E-01 5.34E-01 1.03E+00 4.39E+00 7.37E+00 

eu153 2.34E+02 2.34E+02 2.35E+02 2.35E+02 2.35E+02 2.35E+02 2.35E+02 2.35E+02 

eu154 4.98E+01 4.98E+01 4.89E+01 4.60E+01 3.33E+01 2.23E+01 8.89E-01 1.59E-02 

eu155 1.80E+01 1.80E+01 1.74E+01 1.56E+01 8.71E+00 4.20E+00 1.24E-02 8.45E-06 

gd155 1.75E-01 1.81E-01 8.10E-01 2.62E+00 9.51E+00 1.40E+01 1.82E+01 1.82E+01 

i131 5.32E+00 5.03E+00 2.37E-03 1.15E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 8.89E-02 7.46E-02 3.24E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
A-28

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

i133 1.00E+00 5.33E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 2.97E-03 1.17E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 2.10E-01 2.83E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 4.34E+01 4.34E+01 4.28E+01 4.07E+01 3.15E+01 2.28E+01 1.74E+00 6.94E-02 

kr85m 7.29E-03 3.85E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 5.68E-04 1.80E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 7.41E-03 7.16E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la139 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 

la140 2.08E+00 2.02E+00 1.67E-02 5.38E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 7.97E-02 2.77E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 7.57E-03 1.29E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo100 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 

mo95 1.45E+03 1.45E+03 1.48E+03 1.51E+03 1.51E+03 1.51E+03 1.51E+03 1.51E+03 

mo97 1.71E+03 1.71E+03 1.71E+03 1.71E+03 1.71E+03 1.71E+03 1.71E+03 1.71E+03 

mo98 1.80E+03 1.80E+03 1.80E+03 1.80E+03 1.80E+03 1.80E+03 1.80E+03 1.80E+03 

mo99 2.36E+00 1.93E+00 3.46E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb93m 2.63E-03 2.63E-03 2.76E-03 3.16E-03 5.05E-03 7.01E-03 1.37E-02 1.50E-02 

nb95 2.43E+01 2.43E+01 1.53E+01 1.01E+00 1.41E-07 3.70E-16 0.00E+00 0.00E+00 

nb97 3.34E-02 1.43E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 4.03E-04 1.83E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd143 1.13E+03 1.13E+03 1.14E+03 1.14E+03 1.14E+03 1.14E+03 1.14E+03 1.14E+03 

nd144 3.09E+03 3.09E+03 3.14E+03 3.24E+03 3.35E+03 3.35E+03 3.35E+03 3.35E+03 

nd145 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 

nd147 5.07E+00 4.82E+00 1.75E-02 5.05E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd148 7.93E+02 7.93E+02 7.93E+02 7.93E+02 7.93E+02 7.93E+02 7.93E+02 7.93E+02 

np237 8.99E+02 9.00E+02 9.08E+02 9.08E+02 9.10E+02 9.15E+02 9.89E+02 1.10E+03 

np239 6.20E+01 4.91E+01 3.78E-04 3.78E-04 3.78E-04 3.78E-04 3.76E-04 3.74E-04 

pm147 1.94E+02 1.95E+02 1.87E+02 1.53E+02 5.33E+01 1.42E+01 3.69E-04 6.81E-10 

pr141 2.32E+03 2.32E+03 2.35E+03 2.35E+03 2.35E+03 2.35E+03 2.35E+03 2.35E+03 

pr143 1.34E+01 1.33E+01 1.51E-01 1.20E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.09E-02 1.09E-02 8.75E-03 4.48E-03 1.29E-04 1.52E-06 5.68E-22 0.00E+00 

pr144m 4.33E-05 4.32E-05 3.48E-05 1.78E-05 5.11E-07 6.03E-09 2.26E-24 0.00E+00 
A-29

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

pu238 5.39E+02 5.39E+02 5.50E+02 5.63E+02 5.52E+02 5.31E+02 3.87E+02 2.61E+02 

pu239 4.87E+03 4.88E+03 4.93E+03 4.93E+03 4.93E+03 4.93E+03 4.93E+03 4.92E+03 

pu240 3.44E+03 3.44E+03 3.45E+03 3.45E+03 3.49E+03 3.52E+03 3.65E+03 3.66E+03 

pu241 1.57E+03 1.57E+03 1.55E+03 1.50E+03 1.23E+03 9.67E+02 1.39E+02 1.23E+01 

pu242 1.44E+03 1.44E+03 1.44E+03 1.44E+03 1.44E+03 1.44E+03 1.44E+03 1.44E+03 

rb86 3.86E-02 3.74E-02 1.37E-03 4.92E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 8.63E-04 8.34E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103 7.33E+02 7.33E+02 7.62E+02 7.70E+02 7.70E+02 7.70E+02 7.70E+02 7.70E+02 

rh103m 3.64E-02 3.59E-02 7.45E-03 5.80E-05 3.67E-16 3.69E-30 0.00E+00 0.00E+00 

rh105 9.77E-01 7.21E-01 4.74E-19 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 1.81E-04 1.81E-04 1.53E-04 9.18E-05 6.03E-06 2.01E-07 3.03E-19 5.06E-34 

ru101 1.63E+03 1.63E+03 1.63E+03 1.63E+03 1.63E+03 1.63E+03 1.63E+03 1.63E+03 

ru103 3.71E+01 3.65E+01 7.59E+00 5.90E-02 3.74E-13 3.75E-27 0.00E+00 0.00E+00 

ru105 6.57E-02 3.38E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 1.94E+02 1.93E+02 1.64E+02 9.80E+01 6.45E+00 2.15E-01 3.24E-13 5.41E-28 

sb125 1.26E+01 1.26E+01 1.19E+01 9.83E+00 3.60E+00 1.03E+00 4.46E-05 1.57E-10 

sm147 2.15E+02 2.15E+02 2.27E+02 2.61E+02 3.61E+02 4.00E+02 4.14E+02 4.14E+02 

sm149 1.74E+00 1.93E+00 2.62E+00 2.62E+00 2.62E+00 2.62E+00 2.62E+00 2.62E+00 

sm150 5.73E+02 5.73E+02 5.73E+02 5.73E+02 5.73E+02 5.73E+02 5.73E+02 5.73E+02 

sm151 1.35E+01 1.36E+01 1.37E+01 1.36E+01 1.32E+01 1.27E+01 9.33E+00 6.35E+00 

sm152 1.78E+02 1.78E+02 1.78E+02 1.78E+02 1.78E+02 1.78E+02 1.78E+02 1.78E+02 

sr89 1.49E+01 1.47E+01 4.33E+00 9.96E-02 2.00E-10 2.68E-21 0.00E+00 0.00E+00 

sr90 1.02E+03 1.02E+03 1.02E+03 9.97E+02 9.05E+02 8.03E+02 3.07E+02 9.21E+01 

sr91 1.14E-01 2.89E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 1.46E-02 1.13E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99 1.58E+03 1.58E+03 1.59E+03 1.59E+03 1.59E+03 1.59E+03 1.59E+03 1.59E+03 

tc99m 1.98E-01 1.69E-01 3.05E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te125m 1.62E-01 1.62E-01 1.61E-01 1.37E-01 5.02E-02 1.43E-02 6.22E-07 2.19E-12 

te127 2.43E-02 2.25E-02 1.06E-03 1.85E-04 1.72E-08 1.57E-13 0.00E+00 0.00E+00 

te127m 4.94E-01 4.97E-01 3.04E-01 5.29E-02 4.91E-06 4.48E-11 0.00E+00 0.00E+00 

te129 6.15E-03 1.27E-03 1.61E-04 5.52E-07 4.59E-20 0.00E+00 0.00E+00 0.00E+00 

te129m 1.13E+00 1.11E+00 1.77E-01 6.08E-04 5.05E-17 2.25E-33 0.00E+00 0.00E+00 
A-30

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

te131 5.75E-04 3.77E-04 1.73E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 1.70E-01 1.15E-01 5.25E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 2.88E+00 2.43E+00 1.05E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

u234 1.68E+02 1.68E+02 1.69E+02 1.73E+02 1.90E+02 2.11E+02 3.52E+02 4.76E+02 

u235 3.43E+03 3.43E+03 3.43E+03 3.43E+03 3.43E+03 3.43E+03 3.44E+03 3.44E+03 

u236 7.40E+03 7.40E+03 7.40E+03 7.40E+03 7.40E+03 7.40E+03 7.42E+03 7.44E+03 

u238 9.01E+05 9.01E+05 9.01E+05 9.01E+05 9.01E+05 9.01E+05 9.01E+05 9.01E+05 

xe132 2.63E+03 2.63E+03 2.63E+03 2.63E+03 2.63E+03 2.63E+03 2.63E+03 2.63E+03 

xe133 6.70E+00 6.49E+00 5.65E-05 9.17E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe134 3.28E+03 3.28E+03 3.28E+03 3.28E+03 3.28E+03 3.28E+03 3.28E+03 3.28E+03 

xe135 2.08E-01 1.26E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 1.40E-03 1.89E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe136 4.81E+03 4.81E+03 4.81E+03 4.81E+03 4.81E+03 4.81E+03 4.81E+03 4.81E+03 

y90 2.73E-01 2.70E-01 2.57E-01 2.53E-01 2.30E-01 2.04E-01 7.78E-02 2.34E-02 

y91 2.41E+01 2.40E+01 8.36E+00 3.22E-01 9.90E-09 4.04E-18 0.00E+00 0.00E+00 

y91m 6.27E-03 1.60E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 4.78E-02 2.18E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 1.72E-01 4.72E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr93 1.48E+03 1.48E+03 1.48E+03 1.48E+03 1.48E+03 1.48E+03 1.48E+03 1.48E+03 

zr95 4.43E+01 4.39E+01 1.67E+01 8.53E-01 1.17E-07 3.07E-16 0.00E+00 0.00E+00 

zr97 4.35E-01 1.98E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 

Subtotal 97.6% 97.6% 97.6% 97.6% 97.6% 97.6% 97.5% 97.5% 
B-1

APPENDIX B. PWR RESULTS

Table B.1. Total activity (Ci/MTU) for PWR fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

PWR-1 

(28GWd/MTU) 7.38E+07 5.47E+07 6.76E+06 2.26E+06 5.14E+05 3.46E+05 1.11E+05 3.54E+0

PWR-2 

(39GWd/MTU) 7.49E+07 5.58E+07 7.42E+06 2.71E+06 6.84E+05 4.69E+05 1.52E+05 4.85E+0

PWR-3 

(47GWd/MTU) 7.53E+07 5.61E+07 7.79E+06 2.98E+06 8.02E+05 5.56E+05 1.81E+05 5.81E+0

PWR-Ext 

(72GWd/MTU) 7.88E+07 5.91E+07 8.60E+06 3.68E+06 1.13E+06 7.97E+05 2.64E+05 8.53E+0

Table B.2. Total gamma heat (W/MTU) for PWR fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

PWR-1 

(28GWd/MTU) 1.65E+05 1.12E+05 1.10E+04 2.07E+03 5.37E+02 2.98E+02 9.63E+01 3.07E+0

PWR-2 

(39GWd/MTU) 1.67E+05 1.14E+05 1.20E+04 2.84E+03 8.01E+02 4.26E+02 1.33E+02 4.23E+0

PWR-3 

(47GWd/MTU) 1.69E+05 1.15E+05 1.27E+04 3.37E+03 9.90E+02 5.18E+02 1.59E+02 5.06E+0

PWR-Ext 

(72GWd/MTU) 1.75E+05 1.22E+05 1.49E+04 5.25E+03 1.64E+03 8.09E+02 2.39E+02 7.57E+0

Table B.3. Total decay heat (W/MTU) for PWR fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

PWR-1 

(28GWd/MTU) 3.11E+05 2.06E+05 2.70E+04 9.09E+03 1.49E+03 9.29E+02 4.57E+02 2.55E+0

PWR-2 

(39GWd/MTU) 3.16E+05 2.12E+05 3.07E+04 1.14E+04 2.14E+03 1.36E+03 6.48E+02 3.55E+0

PWR-3 

(47GWd/MTU) 3.19E+05 2.15E+05 3.28E+04 1.27E+04 2.63E+03 1.69E+03 7.91E+02 4.27E+0

PWR-Ext 

(72GWd/MTU) 3.32E+05 2.29E+05 3.92E+04 1.74E+04 4.47E+03 2.95E+03 1.28E+03 6.55E+0
B-2

Table B.4. Total photon emission (photon/s/MTU) for PWR fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

PWR-1 

(28GWd/MTU) 3.38E+18 2.45E+18 1.85E+17 5.64E+16 9.06E+15 5.07E+15 1.81E+15 6.26E+1

PWR-2 

(39GWd/MTU) 3.41E+18 2.49E+18 2.05E+17 6.97E+16 1.27E+16 7.09E+15 2.47E+15 8.54E+1

PWR-3 

(47GWd/MTU) 3.41E+18 2.49E+18 2.16E+17 7.76E+16 1.53E+16 8.57E+15 2.96E+15 1.02E+1

PWR-Ext 

(72GWd/MTU) 3.57E+18 2.64E+18 2.47E+17 1.03E+17 2.36E+16 1.29E+16 4.32E+15 1.47E+1

Table B.5. Total neutron emission (neutron/s/MTU) for PWR fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

PWR-1 

(28GWd/MTU) 4.17E+08 4.17E+08 3.44E+08 2.31E+08 1.58E+08 1.32E+08 3.50E+07 1.16E+0

PWR-2 

(39GWd/MTU) 9.43E+08 9.43E+08 8.08E+08 5.98E+08 4.40E+08 3.66E+08 8.99E+07 2.40E+0

PWR-3 

(47GWd/MTU) 1.37E+09 1.37E+09 1.19E+09 9.17E+08 6.91E+08 5.74E+08 1.39E+08 3.53E+0

PWR-Ext 

(72GWd/MTU) 4.46E+09 4.46E+09 4.12E+09 3.54E+09 2.81E+09 2.31E+09 5.59E+08 1.45E+0

Table B.6. Neutron flux (neutron/cm2

-sec/MTU) for PWR fuel

Group ID 5 hours 1 day 90 days 1 year 5 years 10 years 50 years

100 

years

PWR-1 

(28GWd/MTU) 2.39E+04 2.39E+04 1.97E+04 1.32E+04 9.04E+03 7.55E+03 2.00E+03 6.64E+0

PWR-2 

(39GWd/MTU) 5.39E+04 5.39E+04 4.62E+04 3.42E+04 2.52E+04 2.09E+04 5.14E+03 1.37E+0

PWR-3 

(47GWd/MTU) 7.84E+04 7.84E+04 6.81E+04 5.25E+04 3.95E+04 3.28E+04 7.95E+03 2.02E+0

PWR-Ext 

(72GWd/MTU) 2.55E+05 2.55E+05 2.36E+05 2.02E+05 1.61E+05 1.32E+05 3.20E+04 8.29E+0
B-3

Table B.7. Pu total (gram/MTU) for PWR fuel

Group ID 5 hours 1 day 90 days 1 year 5 years 10 years 50 years

100 

years

PWR-1 

(28GWd/MTU) 9.13E+03 9.15E+03 9.22E+03 9.18E+03 8.98E+03 8.78E+03 8.13E+03 7.99E+0

PWR-2 

(39GWd/MTU) 1.08E+04 1.08E+04 1.09E+04 1.08E+04 1.06E+04 1.03E+04 9.48E+03 9.30E+0

PWR-3 

(47GWd/MTU) 1.19E+04 1.19E+04 1.19E+04 1.19E+04 1.16E+04 1.13E+04 1.03E+04 1.01E+0

PWR-Ext 

(72GWd/MTU) 1.43E+04 1.43E+04 1.44E+04 1.43E+04 1.40E+04 1.37E+04 1.25E+04 1.22E+0

Table B.8. Nuclide activities (Ci/MTU) for PWR-1 (28 GWd/MTU)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

am241 9.96E+01 1.00E+02 1.47E+02 2.90E+02 9.63E+02 1.63E+03 3.57E+03 3.61E+03 

ba137m 8.49E+04 8.49E+04 8.44E+04 8.29E+04 7.56E+04 6.74E+04 2.68E+04 8.48E+03 

ba139 1.71E+05 1.26E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.75E+06 1.68E+06 1.33E+04 4.29E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce141 1.66E+06 1.63E+06 2.45E+05 6.95E+02 2.10E-11 2.64E-28 0.00E+00 0.00E+00 

ce143 1.39E+06 9.35E+05 3.22E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 1.14E+06 1.14E+06 9.20E+05 4.71E+05 1.35E+04 1.59E+02 5.97E-14 0.00E+00 

cm242 3.23E+04 3.23E+04 2.22E+04 6.88E+03 1.65E+01 2.64E+00 2.17E+00 1.69E+00 

cm244 1.33E+03 1.33E+03 1.32E+03 1.28E+03 1.10E+03 9.10E+02 1.97E+02 2.91E+01 

cs134 1.23E+05 1.23E+05 1.13E+05 8.80E+04 2.30E+04 4.30E+03 6.41E-03 3.34E-10 

cs136 3.64E+04 3.49E+04 3.21E+02 1.65E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 8.96E+04 8.96E+04 8.91E+04 8.76E+04 7.99E+04 7.12E+04 2.83E+04 8.96E+03 

i131 1.04E+06 9.80E+05 4.61E+02 2.23E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 1.46E+06 1.23E+06 5.33E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.83E+06 9.71E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 1.32E+05 5.21E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 1.19E+06 1.60E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 8.68E+03 8.68E+03 8.55E+03 8.14E+03 6.29E+03 4.56E+03 3.47E+02 1.39E+01 

kr85m 1.16E+05 6.13E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 3.22E+04 1.02E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
B-4

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

kr88 1.88E+05 1.82E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la140 1.81E+06 1.78E+06 1.53E+04 4.94E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 7.51E+05 2.61E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.85E+05 3.15E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo99 1.81E+06 1.49E+06 2.67E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb95 1.59E+06 1.59E+06 1.02E+06 6.76E+04 9.45E-03 2.49E-11 0.00E+00 0.00E+00 

nb97 1.49E+06 6.37E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 1.33E+06 6.04E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd147 6.51E+05 6.19E+05 2.25E+03 6.49E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

np239 2.20E+07 1.74E+07 1.33E+01 1.33E+01 1.33E+01 1.33E+01 1.33E+01 1.32E+01 

pr143 1.53E+06 1.52E+06 1.72E+04 1.36E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.14E+06 1.14E+06 9.20E+05 4.71E+05 1.35E+04 1.59E+02 5.97E-14 0.00E+00 

pr144m 1.09E+04 1.09E+04 8.78E+03 4.50E+03 1.29E+02 1.52E+00 5.70E-16 0.00E+00 

pu238 1.58E+03 1.59E+03 1.65E+03 1.72E+03 1.70E+03 1.63E+03 1.19E+03 8.03E+02 

pu239 3.35E+02 3.37E+02 3.41E+02 3.41E+02 3.41E+02 3.41E+02 3.41E+02 3.40E+02 

pu240 4.74E+02 4.74E+02 4.74E+02 4.74E+02 4.75E+02 4.75E+02 4.75E+02 4.73E+02 

pu241 1.22E+05 1.22E+05 1.21E+05 1.16E+05 9.58E+04 7.52E+04 1.08E+04 9.58E+02 

rb86 1.65E+03 1.60E+03 5.84E+01 2.10E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 2.10E+05 2.03E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103m 1.66E+06 1.63E+06 3.39E+05 2.64E+03 1.67E-08 1.68E-22 0.00E+00 0.00E+00 

rh105 1.07E+06 7.88E+05 5.17E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 5.07E+05 5.07E+05 4.29E+05 2.57E+05 1.69E+04 5.62E+02 8.48E-10 1.42E-24 

ru103 1.67E+06 1.65E+06 3.43E+05 2.67E+03 1.69E-08 1.70E-22 0.00E+00 0.00E+00 

ru105 5.83E+05 3.00E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 5.07E+05 5.07E+05 4.29E+05 2.57E+05 1.69E+04 5.62E+02 8.48E-10 1.42E-24 

sr89 8.80E+05 8.70E+05 2.57E+05 5.90E+03 1.18E-05 1.59E-16 0.00E+00 0.00E+00 

sr90 6.37E+04 6.37E+04 6.33E+04 6.22E+04 5.65E+04 5.01E+04 1.91E+04 5.75E+03 

sr91 7.93E+05 2.02E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 3.47E+05 2.68E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99m 1.68E+06 1.43E+06 2.58E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te127 9.45E+04 8.69E+04 4.09E+03 7.12E+02 6.61E-02 6.02E-07 0.00E+00 0.00E+00 

te127m 6.78E+03 6.82E+03 4.18E+03 7.27E+02 6.75E-02 6.15E-07 0.00E+00 0.00E+00 
B-5

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

te129 1.90E+05 3.91E+04 4.93E+03 1.69E+01 1.41E-12 0.00E+00 0.00E+00 0.00E+00 

te129m 4.97E+04 4.90E+04 7.81E+03 2.69E+01 2.23E-12 9.95E-29 0.00E+00 0.00E+00 

te131 5.02E+04 3.29E+04 1.51E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 1.86E+05 1.25E+05 5.74E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 1.41E+06 1.19E+06 5.17E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe133 2.11E+06 2.04E+06 1.77E+01 2.87E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135 8.08E+05 5.02E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 2.04E+05 2.75E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y90 6.65E+04 6.60E+04 6.34E+04 6.22E+04 5.65E+04 5.01E+04 1.91E+04 5.75E+03 

y91 1.15E+06 1.15E+06 4.00E+05 1.54E+04 4.74E-04 1.93E-13 0.00E+00 0.00E+00 

y91m 5.09E+05 1.30E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 8.68E+05 3.96E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 1.04E+06 2.85E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr95 1.63E+06 1.61E+06 6.15E+05 3.13E+04 4.29E-03 1.13E-11 0.00E+00 0.00E+00 

zr97 1.39E+06 6.34E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Totala 7.38E+07 5.47E+07 6.76E+06 2.26E+06 5.14E+05 3.46E+05 1.11E+05 3.54E+04 

Subtotalb 93.0% 94.5% 97.0% 93.4% 89.3% 95.1% 99.1% 99.4% 

a Total includes contributions from all actinides and fission products in the fuel. b Subtotal is the percent contribution of nuclides listed in the table to the total.

Table B.9. Nuclide activities (Ci/MTU) for PWR-2 (39 GWd/MTU)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

am241 1.59E+02 1.60E+02 2.21E+02 4.06E+02 1.28E+03 2.15E+03 4.66E+03 4.70E+03 

ba137m 1.17E+05 1.17E+05 1.17E+05 1.14E+05 1.04E+05 9.30E+04 3.70E+04 1.17E+04 

ba139 1.70E+05 1.25E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.73E+06 1.66E+06 1.32E+04 4.25E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce141 1.64E+06 1.62E+06 2.43E+05 6.90E+02 2.08E-11 2.62E-28 0.00E+00 0.00E+00 

ce143 1.37E+06 9.21E+05 3.18E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 1.25E+06 1.25E+06 1.01E+06 5.15E+05 1.48E+04 1.74E+02 6.52E-14 0.00E+00 

cm242 5.85E+04 5.85E+04 4.01E+04 1.25E+04 2.95E+01 4.40E+00 3.61E+00 2.82E+00 

cm244 3.77E+03 3.77E+03 3.74E+03 3.63E+03 3.11E+03 2.57E+03 5.57E+02 8.23E+01 
B-6

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

cs134 2.04E+05 2.04E+05 1.88E+05 1.46E+05 3.81E+04 7.13E+03 1.06E-02 5.53E-10 

cs136 5.10E+04 4.90E+04 4.51E+02 2.31E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 1.24E+05 1.24E+05 1.23E+05 1.21E+05 1.10E+05 9.82E+04 3.91E+04 1.24E+04 

i131 1.04E+06 9.81E+05 4.62E+02 2.23E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 1.46E+06 1.23E+06 5.33E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.82E+06 9.67E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 1.31E+05 5.16E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 1.19E+06 1.60E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 1.16E+04 1.16E+04 1.14E+04 1.09E+04 8.39E+03 6.08E+03 4.63E+02 1.85E+01 

kr85m 1.11E+05 5.88E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 3.07E+04 9.71E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 1.79E+05 1.73E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la140 1.81E+06 1.78E+06 1.52E+04 4.89E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 7.43E+05 2.58E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.82E+05 3.11E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo99 1.81E+06 1.48E+06 2.66E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb95 1.61E+06 1.61E+06 1.02E+06 6.73E+04 9.40E-03 2.47E-11 0.00E+00 0.00E+00 

nb97 1.48E+06 6.31E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 1.31E+06 5.98E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd147 6.50E+05 6.18E+05 2.24E+03 6.48E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

np239 2.18E+07 1.73E+07 2.75E+01 2.75E+01 2.75E+01 2.75E+01 2.74E+01 2.73E+01 

pr143 1.51E+06 1.49E+06 1.69E+04 1.34E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.25E+06 1.25E+06 1.01E+06 5.15E+05 1.48E+04 1.74E+02 6.52E-14 0.00E+00 

pr144m 1.19E+04 1.19E+04 9.59E+03 4.91E+03 1.41E+02 1.66E+00 6.23E-16 0.00E+00 

pu238 3.20E+03 3.21E+03 3.32E+03 3.44E+03 3.39E+03 3.26E+03 2.38E+03 1.61E+03 

pu239 3.68E+02 3.69E+02 3.74E+02 3.74E+02 3.74E+02 3.74E+02 3.73E+02 3.73E+02 

pu240 5.83E+02 5.83E+02 5.83E+02 5.83E+02 5.84E+02 5.85E+02 5.89E+02 5.87E+02 

pu241 1.58E+05 1.58E+05 1.56E+05 1.51E+05 1.24E+05 9.75E+04 1.40E+04 1.24E+03 

rb86 2.32E+03 2.25E+03 8.22E+01 2.96E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 2.00E+05 1.93E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103m 1.71E+06 1.69E+06 3.51E+05 2.73E+03 1.73E-08 1.73E-22 0.00E+00 0.00E+00 

rh105 1.12E+06 8.26E+05 5.43E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
B-7

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

rh106 6.34E+05 6.33E+05 5.36E+05 3.21E+05 2.11E+04 7.03E+02 1.06E-09 1.77E-24 

ru103 1.73E+06 1.71E+06 3.55E+05 2.76E+03 1.75E-08 1.75E-22 0.00E+00 0.00E+00 

ru105 6.09E+05 3.13E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 6.34E+05 6.33E+05 5.36E+05 3.21E+05 2.11E+04 7.03E+02 1.06E-09 1.77E-24 

sr89 8.41E+05 8.32E+05 2.45E+05 5.64E+03 1.13E-05 1.52E-16 0.00E+00 0.00E+00 

sr90 8.62E+04 8.62E+04 8.57E+04 8.42E+04 7.65E+04 6.78E+04 2.59E+04 7.78E+03 

sr91 7.59E+05 1.93E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 3.34E+05 2.58E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99m 1.67E+06 1.42E+06 2.57E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te127 9.65E+04 8.86E+04 4.34E+03 7.56E+02 7.02E-02 6.40E-07 0.00E+00 0.00E+00 

te127m 7.23E+03 7.27E+03 4.44E+03 7.72E+02 7.17E-02 6.53E-07 0.00E+00 0.00E+00 

te129 1.93E+05 3.98E+04 5.03E+03 1.73E+01 1.44E-12 0.00E+00 0.00E+00 0.00E+00 

te129m 5.07E+04 5.00E+04 7.97E+03 2.74E+01 2.27E-12 1.01E-28 0.00E+00 0.00E+00 

te131 5.05E+04 3.30E+04 1.51E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 1.87E+05 1.26E+05 5.77E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 1.41E+06 1.19E+06 5.17E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe133 2.10E+06 2.03E+06 1.76E+01 2.86E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135 8.30E+05 5.07E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 2.04E+05 2.74E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y90 9.01E+04 8.94E+04 8.57E+04 8.42E+04 7.65E+04 6.78E+04 2.59E+04 7.78E+03 

y91 1.12E+06 1.11E+06 3.87E+05 1.49E+04 4.59E-04 1.87E-13 0.00E+00 0.00E+00 

y91m 4.87E+05 1.24E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 8.36E+05 3.82E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 1.01E+06 2.76E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr95 1.62E+06 1.60E+06 6.12E+05 3.12E+04 4.26E-03 1.12E-11 0.00E+00 0.00E+00 

zr97 1.38E+06 6.28E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 7.49E+07 5.58E+07 7.42E+06 2.71E+06 6.84E+05 4.69E+05 1.52E+05 4.85E+04 

Subtotal 92.1% 93.7% 96.9% 93.7% 90.5% 95.5% 99.3% 99.6% 
B-8

Table B.10. Nuclide activities (Ci/MTU) for PWR-3 (47 GWd/MTU)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

am241 2.03E+02 2.04E+02 2.74E+02 4.83E+02 1.47E+03 2.46E+03 5.30E+03 5.35E+03 

ba137m 1.40E+05 1.40E+05 1.39E+05 1.37E+05 1.25E+05 1.11E+05 4.43E+04 1.40E+04 

ba139 1.69E+05 1.25E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.73E+06 1.66E+06 1.32E+04 4.24E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce141 1.64E+06 1.62E+06 2.42E+05 6.88E+02 2.08E-11 2.62E-28 0.00E+00 0.00E+00 

ce143 1.37E+06 9.19E+05 3.17E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 1.30E+06 1.30E+06 1.04E+06 5.35E+05 1.53E+04 1.81E+02 6.78E-14 0.00E+00 

cm242 7.62E+04 7.61E+04 5.23E+04 1.62E+04 3.85E+01 5.77E+00 4.73E+00 3.70E+00 

cm244 5.93E+03 5.93E+03 5.88E+03 5.71E+03 4.90E+03 4.05E+03 8.76E+02 1.29E+02 

cs134 2.63E+05 2.63E+05 2.42E+05 1.88E+05 4.91E+04 9.18E+03 1.37E-02 7.13E-10 

cs136 6.30E+04 6.04E+04 5.56E+02 2.85E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 1.48E+05 1.48E+05 1.47E+05 1.45E+05 1.32E+05 1.18E+05 4.68E+04 1.48E+04 

i131 1.04E+06 9.79E+05 4.61E+02 2.23E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 1.46E+06 1.22E+06 5.32E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.82E+06 9.66E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 1.31E+05 5.16E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 1.19E+06 1.60E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 1.37E+04 1.37E+04 1.35E+04 1.29E+04 9.96E+03 7.22E+03 5.49E+02 2.19E+01 

kr85m 1.11E+05 5.85E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 3.05E+04 9.66E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 1.78E+05 1.72E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la140 1.81E+06 1.78E+06 1.51E+04 4.88E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 7.41E+05 2.57E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.82E+05 3.10E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo99 1.81E+06 1.48E+06 2.66E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb95 1.62E+06 1.62E+06 1.02E+06 6.73E+04 9.40E-03 2.47E-11 0.00E+00 0.00E+00 

nb97 1.47E+06 6.30E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 1.31E+06 5.97E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd147 6.51E+05 6.20E+05 2.25E+03 6.49E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

np239 2.13E+07 1.69E+07 3.74E+01 3.74E+01 3.74E+01 3.74E+01 3.73E+01 3.71E+01 
B-9

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

pr143 1.50E+06 1.49E+06 1.69E+04 1.34E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.30E+06 1.30E+06 1.04E+06 5.35E+05 1.53E+04 1.81E+02 6.78E-14 0.00E+00 

pr144m 1.24E+04 1.24E+04 9.97E+03 5.11E+03 1.46E+02 1.73E+00 6.47E-16 0.00E+00 

pu238 4.68E+03 4.69E+03 4.83E+03 4.98E+03 4.91E+03 4.72E+03 3.44E+03 2.32E+03 

pu239 3.91E+02 3.93E+02 3.97E+02 3.97E+02 3.97E+02 3.97E+02 3.97E+02 3.96E+02 

pu240 6.38E+02 6.38E+02 6.38E+02 6.38E+02 6.40E+02 6.42E+02 6.48E+02 6.47E+02 

pu241 1.79E+05 1.79E+05 1.77E+05 1.71E+05 1.41E+05 1.10E+05 1.59E+04 1.41E+03 

rb86 2.81E+03 2.73E+03 9.95E+01 3.59E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.98E+05 1.92E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103m 1.72E+06 1.70E+06 3.52E+05 2.74E+03 1.73E-08 1.74E-22 0.00E+00 0.00E+00 

rh105 1.13E+06 8.34E+05 5.48E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 6.87E+05 6.86E+05 5.81E+05 3.48E+05 2.29E+04 7.62E+02 1.15E-09 1.92E-24 

ru103 1.74E+06 1.72E+06 3.56E+05 2.77E+03 1.75E-08 1.76E-22 0.00E+00 0.00E+00 

ru105 6.12E+05 3.15E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 6.87E+05 6.86E+05 5.81E+05 3.48E+05 2.29E+04 7.62E+02 1.15E-09 1.92E-24 

sr89 8.35E+05 8.26E+05 2.44E+05 5.61E+03 1.12E-05 1.51E-16 0.00E+00 0.00E+00 

sr90 1.04E+05 1.04E+05 1.03E+05 1.01E+05 9.19E+04 8.14E+04 3.11E+04 9.34E+03 

sr91 7.54E+05 1.92E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 3.32E+05 2.57E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99m 1.67E+06 1.42E+06 2.57E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te127 9.64E+04 8.86E+04 4.51E+03 7.84E+02 7.28E-02 6.64E-07 0.00E+00 0.00E+00 

te127m 7.52E+03 7.56E+03 4.60E+03 8.00E+02 7.43E-02 6.77E-07 0.00E+00 0.00E+00 

te129 1.93E+05 3.98E+04 5.02E+03 1.73E+01 1.43E-12 0.00E+00 0.00E+00 0.00E+00 

te129m 5.06E+04 4.99E+04 7.96E+03 2.74E+01 2.27E-12 1.01E-28 0.00E+00 0.00E+00 

te131 5.02E+04 3.28E+04 1.51E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 1.86E+05 1.25E+05 5.74E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 1.41E+06 1.19E+06 5.16E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe133 2.10E+06 2.03E+06 1.76E+01 2.86E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135 8.53E+05 5.12E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 2.04E+05 2.74E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y90 1.08E+05 1.07E+05 1.03E+05 1.01E+05 9.19E+04 8.15E+04 3.11E+04 9.34E+03 

y91 1.11E+06 1.11E+06 3.85E+05 1.48E+04 4.56E-04 1.86E-13 0.00E+00 0.00E+00 
B-10

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

y91m 4.85E+05 1.24E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 8.32E+05 3.80E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 1.00E+06 2.75E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr95 1.62E+06 1.60E+06 6.12E+05 3.12E+04 4.26E-03 1.12E-11 0.00E+00 0.00E+00 

zr97 1.38E+06 6.27E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 7.53E+07 5.61E+07 7.79E+06 2.98E+06 8.02E+05 5.56E+05 1.81E+05 5.81E+04 

Subtotal 91.5% 93.2% 96.7% 93.3% 90.9% 95.9% 100.0% 99.5% 

Table B.11. Nuclide activities (Ci/MTU) for PWR-Ext (72 GWd/MTU)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

am241 2.89E+02 2.90E+02 3.77E+02 6.40E+02 1.88E+03 3.11E+03 6.68E+03 6.73E+03 

ba137m 2.10E+05 2.10E+05 2.09E+05 2.05E+05 1.87E+05 1.67E+05 6.64E+04 2.10E+04 

ba139 1.65E+05 1.22E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.68E+06 1.61E+06 1.28E+04 4.12E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce141 1.59E+06 1.57E+06 2.35E+05 6.67E+02 2.02E-11 2.54E-28 0.00E+00 0.00E+00 

ce143 1.31E+06 8.76E+05 3.02E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 1.29E+06 1.29E+06 1.04E+06 5.33E+05 1.53E+04 1.80E+02 6.75E-14 0.00E+00 

cm242 1.37E+05 1.37E+05 9.38E+04 2.91E+04 6.70E+01 8.34E+00 6.83E+00 5.34E+00 

cm244 2.37E+04 2.37E+04 2.35E+04 2.29E+04 1.96E+04 1.62E+04 3.51E+03 5.18E+02 

cs134 4.83E+05 4.83E+05 4.45E+05 3.46E+05 9.03E+04 1.69E+04 2.52E-02 1.31E-09 

cs136 1.04E+05 9.98E+04 9.19E+02 4.71E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 2.22E+05 2.22E+05 2.21E+05 2.17E+05 1.98E+05 1.76E+05 7.01E+04 2.22E+04 

i131 1.05E+06 9.87E+05 4.65E+02 2.25E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 1.46E+06 1.22E+06 5.31E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.80E+06 9.54E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 1.26E+05 4.98E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 1.18E+06 1.59E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 1.85E+04 1.85E+04 1.82E+04 1.74E+04 1.34E+04 9.73E+03 7.40E+02 2.96E+01 

kr85m 9.66E+04 5.10E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 2.60E+04 8.22E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
B-11

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

kr88 1.50E+05 1.45E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la140 1.80E+06 1.76E+06 1.47E+04 4.75E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 7.19E+05 2.49E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.75E+05 2.98E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo99 1.79E+06 1.47E+06 2.64E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb95 1.53E+06 1.53E+06 9.58E+05 6.32E+04 8.83E-03 2.32E-11 0.00E+00 0.00E+00 

nb97 1.43E+06 6.11E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 1.27E+06 5.79E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd147 6.45E+05 6.14E+05 2.23E+03 6.43E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

np239 2.29E+07 1.81E+07 9.38E+01 9.38E+01 9.38E+01 9.38E+01 9.34E+01 9.30E+01 

pr143 1.43E+06 1.42E+06 1.61E+04 1.28E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.29E+06 1.29E+06 1.04E+06 5.33E+05 1.53E+04 1.80E+02 6.75E-14 0.00E+00 

pr144m 1.24E+04 1.23E+04 9.93E+03 5.08E+03 1.46E+02 1.72E+00 6.44E-16 0.00E+00 

pu238 1.09E+04 1.09E+04 1.12E+04 1.15E+04 1.12E+04 1.08E+04 7.88E+03 5.31E+03 

pu239 4.06E+02 4.08E+02 4.12E+02 4.12E+02 4.12E+02 4.12E+02 4.12E+02 4.12E+02 

pu240 8.03E+02 8.03E+02 8.03E+02 8.05E+02 8.14E+02 8.23E+02 8.54E+02 8.58E+02 

pu241 2.25E+05 2.25E+05 2.22E+05 2.14E+05 1.77E+05 1.39E+05 1.99E+04 1.77E+03 

rb86 4.54E+03 4.41E+03 1.61E+02 5.80E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.68E+05 1.62E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103m 1.85E+06 1.83E+06 3.80E+05 2.95E+03 1.87E-08 1.88E-22 0.00E+00 0.00E+00 

rh105 1.27E+06 9.36E+05 6.15E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 9.21E+05 9.20E+05 7.79E+05 4.67E+05 3.07E+04 1.02E+03 1.54E-09 2.57E-24 

ru103 1.87E+06 1.85E+06 3.84E+05 2.98E+03 1.89E-08 1.90E-22 0.00E+00 0.00E+00 

ru105 6.91E+05 3.56E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 9.21E+05 9.20E+05 7.79E+05 4.67E+05 3.07E+04 1.02E+03 1.54E-09 2.57E-24 

sr89 7.01E+05 6.94E+05 2.05E+05 4.70E+03 9.43E-06 1.27E-16 0.00E+00 0.00E+00 

sr90 1.44E+05 1.44E+05 1.43E+05 1.40E+05 1.28E+05 1.13E+05 4.32E+04 1.30E+04 

sr91 6.54E+05 1.66E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 2.95E+05 2.28E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99m 1.67E+06 1.41E+06 2.55E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te127 1.02E+05 9.39E+04 4.63E+03 8.05E+02 7.48E-02 6.82E-07 0.00E+00 0.00E+00 

te127m 7.71E+03 7.75E+03 4.73E+03 8.22E+02 7.63E-02 6.96E-07 0.00E+00 0.00E+00 
B-12

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

te129 2.03E+05 4.20E+04 5.30E+03 1.82E+01 1.51E-12 0.00E+00 0.00E+00 0.00E+00 

te129m 5.34E+04 5.26E+04 8.39E+03 2.89E+01 2.40E-12 1.07E-28 0.00E+00 0.00E+00 

te131 5.19E+04 3.40E+04 1.56E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 1.93E+05 1.30E+05 5.95E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 1.41E+06 1.19E+06 5.16E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe133 2.08E+06 2.01E+06 1.74E+01 2.83E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135 8.31E+05 5.05E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 2.03E+05 2.73E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y90 1.51E+05 1.50E+05 1.43E+05 1.41E+05 1.28E+05 1.13E+05 4.32E+04 1.30E+04 

y91 9.60E+05 9.55E+05 3.33E+05 1.28E+04 3.95E-04 1.61E-13 0.00E+00 0.00E+00 

y91m 4.20E+05 1.07E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 7.38E+05 3.37E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 9.13E+05 2.50E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr95 1.52E+06 1.51E+06 5.74E+05 2.93E+04 4.00E-03 1.05E-11 0.00E+00 0.00E+00 

zr97 1.34E+06 6.09E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 7.88E+07 5.91E+07 8.60E+06 3.68E+06 1.13E+06 7.97E+05 2.64E+05 8.53E+04 

Subtotal 89.7% 91.5% 96.7% 94.3% 92.9% 96.4% 99.6% 99.4% 

Table B.12. Nuclide mass (gram/MTU) for PWR-1 (28 GWd/MTU)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

ag109 6.56E+01 6.57E+01 6.58E+01 6.58E+01 6.58E+01 6.58E+01 6.58E+01 6.58E+01 

am241 2.91E+01 2.92E+01 4.30E+01 8.45E+01 2.81E+02 4.76E+02 1.04E+03 1.05E+03 

am242 7.01E-02 3.08E-02 4.14E-06 4.12E-06 4.04E-06 3.94E-06 3.24E-06 2.53E-06 

am242m 3.21E-01 3.21E-01 3.21E-01 3.19E-01 3.13E-01 3.06E-01 2.51E-01 1.96E-01 

am243 6.66E+01 6.66E+01 6.66E+01 6.66E+01 6.66E+01 6.66E+01 6.63E+01 6.60E+01 

ba137 2.74E+01 2.75E+01 3.33E+01 5.09E+01 1.40E+02 2.40E+02 7.33E+02 9.57E+02 

ba137m 1.58E-04 1.58E-04 1.57E-04 1.54E-04 1.41E-04 1.25E-04 4.99E-05 1.58E-05 

ba138 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 

ba139 1.05E-02 7.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 2.39E+01 2.29E+01 1.82E-01 5.86E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
B-13

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

ce140 1.01E+03 1.02E+03 1.04E+03 1.04E+03 1.04E+03 1.04E+03 1.04E+03 1.04E+03 

ce141 5.81E+01 5.73E+01 8.59E+00 2.44E-02 7.37E-16 9.28E-33 0.00E+00 0.00E+00 

ce142 9.55E+02 9.55E+02 9.55E+02 9.55E+02 9.55E+02 9.55E+02 9.55E+02 9.55E+02 

ce143 2.10E+00 1.41E+00 4.86E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 3.59E+02 3.59E+02 2.89E+02 1.48E+02 4.24E+00 5.00E-02 1.88E-17 0.00E+00 

cm242 9.74E+00 9.74E+00 6.69E+00 2.08E+00 4.99E-03 7.98E-04 6.54E-04 5.11E-04 

cm243 1.74E-01 1.74E-01 1.73E-01 1.70E-01 1.54E-01 1.37E-01 5.28E-02 1.61E-02 

cm244 1.65E+01 1.65E+01 1.63E+01 1.59E+01 1.36E+01 1.12E+01 2.43E+00 3.60E-01 

cm245 8.07E-01 8.07E-01 8.07E-01 8.07E-01 8.06E-01 8.06E-01 8.03E-01 8.00E-01 

cs133 9.71E+02 9.72E+02 9.84E+02 9.84E+02 9.84E+02 9.84E+02 9.84E+02 9.84E+02 

cs134 9.53E+01 9.52E+01 8.77E+01 6.81E+01 1.78E+01 3.33E+00 4.96E-06 2.58E-13 

cs136 4.99E-01 4.78E-01 4.40E-03 2.26E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 1.03E+03 1.03E+03 1.03E+03 1.01E+03 9.20E+02 8.20E+02 3.26E+02 1.03E+02 

eu151 9.62E-03 9.80E-03 2.99E-02 9.16E-02 4.14E-01 8.02E-01 3.43E+00 5.76E+00 

eu153 9.59E+01 9.61E+01 9.68E+01 9.68E+01 9.68E+01 9.68E+01 9.68E+01 9.68E+01 

eu154 1.86E+01 1.86E+01 1.82E+01 1.72E+01 1.24E+01 8.32E+00 3.32E-01 5.92E-03 

eu155 6.35E+00 6.35E+00 6.13E+00 5.49E+00 3.06E+00 1.48E+00 4.35E-03 2.98E-06 

gd155 3.87E-02 4.07E-02 2.62E-01 8.99E-01 3.32E+00 4.91E+00 6.38E+00 6.39E+00 

i131 8.35E+00 7.88E+00 3.71E-03 1.80E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 1.41E-01 1.19E-01 5.15E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.61E+00 8.57E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 4.93E-03 1.95E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 3.36E-01 4.53E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 2.22E+01 2.22E+01 2.19E+01 2.08E+01 1.61E+01 1.17E+01 8.87E-01 3.54E-02 

kr85m 1.41E-02 7.45E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 1.14E-03 3.60E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 1.50E-02 1.45E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la139 1.04E+03 1.04E+03 1.04E+03 1.04E+03 1.04E+03 1.04E+03 1.04E+03 1.04E+03 

la140 3.26E+00 3.21E+00 2.75E-02 8.88E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 1.32E-01 4.59E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.27E-02 2.16E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo100 7.93E+02 7.93E+02 7.93E+02 7.93E+02 7.93E+02 7.93E+02 7.93E+02 7.93E+02 
B-14

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

mo95 5.34E+02 5.35E+02 5.96E+02 6.48E+02 6.51E+02 6.51E+02 6.51E+02 6.51E+02 

mo97 6.86E+02 6.87E+02 6.87E+02 6.87E+02 6.87E+02 6.87E+02 6.87E+02 6.87E+02 

mo98 7.00E+02 7.00E+02 7.00E+02 7.00E+02 7.00E+02 7.00E+02 7.00E+02 7.00E+02 

mo99 3.78E+00 3.09E+00 5.55E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb93m 3.12E-04 3.12E-04 3.74E-04 5.60E-04 1.45E-03 2.37E-03 5.53E-03 6.14E-03 

nb95 4.05E+01 4.05E+01 2.59E+01 1.72E+00 2.40E-07 6.33E-16 0.00E+00 0.00E+00 

nb97 5.54E-02 2.37E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 6.69E-04 3.05E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd143 6.91E+02 6.92E+02 7.15E+02 7.15E+02 7.15E+02 7.15E+02 7.15E+02 7.15E+02 

nd144 7.19E+02 7.19E+02 7.89E+02 9.30E+02 1.07E+03 1.08E+03 1.08E+03 1.08E+03 

nd145 5.78E+02 5.78E+02 5.78E+02 5.78E+02 5.78E+02 5.78E+02 5.78E+02 5.78E+02 

nd147 8.04E+00 7.65E+00 2.78E-02 8.02E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd148 3.16E+02 3.16E+02 3.16E+02 3.16E+02 3.16E+02 3.16E+02 3.16E+02 3.16E+02 

np237 3.31E+02 3.32E+02 3.40E+02 3.40E+02 3.42E+02 3.45E+02 3.99E+02 4.82E+02 

np239 9.47E+01 7.50E+01 5.74E-05 5.74E-05 5.73E-05 5.73E-05 5.71E-05 5.68E-05 

pm147 1.78E+02 1.79E+02 1.75E+02 1.43E+02 4.98E+01 1.33E+01 3.44E-04 6.36E-10 

pr141 8.91E+02 8.92E+02 9.40E+02 9.49E+02 9.49E+02 9.49E+02 9.49E+02 9.49E+02 

pr143 2.27E+01 2.25E+01 2.55E-01 2.03E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.51E-02 1.51E-02 1.22E-02 6.23E-03 1.79E-04 2.11E-06 7.90E-22 0.00E+00 

pr144m 6.02E-05 6.01E-05 4.84E-05 2.48E-05 7.11E-07 8.38E-09 3.14E-24 0.00E+00 

pu238 9.23E+01 9.26E+01 9.62E+01 1.00E+02 9.90E+01 9.52E+01 6.95E+01 4.68E+01 

pu239 5.40E+03 5.42E+03 5.50E+03 5.50E+03 5.50E+03 5.50E+03 5.49E+03 5.48E+03 

pu240 2.09E+03 2.09E+03 2.09E+03 2.09E+03 2.09E+03 2.09E+03 2.09E+03 2.08E+03 

pu241 1.18E+03 1.18E+03 1.16E+03 1.12E+03 9.23E+02 7.24E+02 1.04E+02 9.23E+00 

pu242 3.72E+02 3.72E+02 3.72E+02 3.72E+02 3.72E+02 3.72E+02 3.72E+02 3.72E+02 

rb86 2.02E-02 1.96E-02 7.16E-04 2.58E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.75E-03 1.69E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103 3.83E+02 3.84E+02 4.24E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 

rh103m 5.09E-02 5.02E-02 1.04E-02 8.10E-05 5.13E-16 5.15E-30 0.00E+00 0.00E+00 

rh105 1.26E+00 9.33E-01 6.13E-19 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 1.43E-04 1.43E-04 1.21E-04 7.26E-05 4.77E-06 1.59E-07 2.40E-19 4.00E-34 

ru101 6.65E+02 6.65E+02 6.65E+02 6.65E+02 6.65E+02 6.65E+02 6.65E+02 6.65E+02 
B-15

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

ru103 5.18E+01 5.11E+01 1.06E+01 8.25E-02 5.22E-13 5.25E-27 0.00E+00 0.00E+00 

ru105 8.67E-02 4.46E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 1.53E+02 1.53E+02 1.29E+02 7.75E+01 5.10E+00 1.70E-01 2.56E-13 4.27E-28 

sb125 8.12E+00 8.12E+00 7.73E+00 6.40E+00 2.34E+00 6.67E-01 2.90E-05 1.02E-10 

sm147 5.56E+01 5.57E+01 6.72E+01 9.88E+01 1.92E+02 2.29E+02 2.42E+02 2.42E+02 

sm149 2.20E+00 2.49E+00 3.51E+00 3.51E+00 3.51E+00 3.51E+00 3.51E+00 3.51E+00 

sm150 2.45E+02 2.45E+02 2.45E+02 2.45E+02 2.45E+02 2.45E+02 2.45E+02 2.45E+02 

sm151 1.05E+01 1.06E+01 1.07E+01 1.06E+01 1.03E+01 9.91E+00 7.28E+00 4.96E+00 

sm152 9.62E+01 9.62E+01 9.62E+01 9.62E+01 9.62E+01 9.62E+01 9.62E+01 9.62E+01 

sr89 3.03E+01 3.00E+01 8.84E+00 2.03E-01 4.07E-10 5.47E-21 0.00E+00 0.00E+00 

sr90 4.62E+02 4.62E+02 4.59E+02 4.51E+02 4.09E+02 3.63E+02 1.39E+02 4.16E+01 

sr91 2.22E-01 5.64E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 2.76E-02 2.13E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99 6.93E+02 6.94E+02 6.97E+02 6.97E+02 6.97E+02 6.97E+02 6.97E+02 6.97E+02 

tc99m 3.18E-01 2.71E-01 4.89E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te125m 9.44E-02 9.46E-02 1.01E-01 8.90E-02 3.27E-02 9.31E-03 4.05E-07 1.43E-12 

te127 3.58E-02 3.29E-02 1.55E-03 2.70E-04 2.50E-08 2.28E-13 0.00E+00 0.00E+00 

te127m 7.18E-01 7.23E-01 4.43E-01 7.70E-02 7.15E-06 6.52E-11 0.00E+00 0.00E+00 

te129 9.08E-03 1.87E-03 2.35E-04 8.09E-07 6.72E-20 0.00E+00 0.00E+00 0.00E+00 

te129m 1.65E+00 1.63E+00 2.59E-01 8.91E-04 7.40E-17 3.30E-33 0.00E+00 0.00E+00 

te131 8.74E-04 5.72E-04 2.62E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 2.59E-01 1.74E-01 7.98E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 4.57E+00 3.85E+00 1.67E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

u234 1.65E+02 1.65E+02 1.65E+02 1.66E+02 1.69E+02 1.73E+02 1.98E+02 2.20E+02 

u235 9.00E+03 9.00E+03 9.00E+03 9.00E+03 9.00E+03 9.00E+03 9.01E+03 9.02E+03 

u236 3.56E+03 3.56E+03 3.56E+03 3.56E+03 3.56E+03 3.56E+03 3.57E+03 3.58E+03 

u238 9.49E+05 9.49E+05 9.49E+05 9.49E+05 9.49E+05 9.49E+05 9.49E+05 9.49E+05 

xe132 9.00E+02 9.01E+02 9.05E+02 9.05E+02 9.05E+02 9.05E+02 9.05E+02 9.05E+02 

xe133 1.13E+01 1.09E+01 9.43E-05 1.53E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe134 1.29E+03 1.29E+03 1.29E+03 1.29E+03 1.29E+03 1.29E+03 1.29E+03 1.29E+03 

xe135 3.18E-01 1.98E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 2.24E-03 3.02E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
B-16

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

xe136 2.01E+03 2.01E+03 2.01E+03 2.01E+03 2.01E+03 2.01E+03 2.01E+03 2.01E+03 

y90 1.22E-01 1.21E-01 1.16E-01 1.14E-01 1.04E-01 9.21E-02 3.52E-02 1.06E-02 

y91 4.70E+01 4.68E+01 1.63E+01 6.28E-01 1.93E-08 7.88E-18 0.00E+00 0.00E+00 

y91m 1.23E-02 3.12E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 9.01E-02 4.11E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 3.13E-01 8.59E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr93 6.05E+02 6.05E+02 6.05E+02 6.05E+02 6.05E+02 6.05E+02 6.05E+02 6.05E+02 

zr95 7.57E+01 7.50E+01 2.86E+01 1.46E+00 2.00E-07 5.25E-16 0.00E+00 0.00E+00 

zr97 7.22E-01 3.29E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 

Subtotal 99.2% 99.2% 99.2% 99.2% 99.1% 99.1% 99.1% 99.1% 

Table B.13. Nuclide mass (gram/MTU) for PWR-2 (39 GWd/MTU)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

ag109 9.19E+01 9.20E+01 9.21E+01 9.21E+01 9.21E+01 9.21E+01 9.21E+01 9.21E+01 

am241 4.64E+01 4.66E+01 6.45E+01 1.18E+02 3.73E+02 6.26E+02 1.36E+03 1.37E+03 

am242 1.06E-01 4.66E-02 6.89E-06 6.86E-06 6.73E-06 6.56E-06 5.39E-06 4.22E-06 

am242m 5.34E-01 5.34E-01 5.34E-01 5.32E-01 5.21E-01 5.09E-01 4.18E-01 3.27E-01 

am243 1.38E+02 1.38E+02 1.38E+02 1.38E+02 1.38E+02 1.38E+02 1.37E+02 1.37E+02 

ba137 5.11E+01 5.11E+01 5.91E+01 8.35E+01 2.06E+02 3.44E+02 1.03E+03 1.33E+03 

ba137m 2.18E-04 2.18E-04 2.16E-04 2.13E-04 1.94E-04 1.73E-04 6.88E-05 2.18E-05 

ba138 1.53E+03 1.53E+03 1.53E+03 1.53E+03 1.53E+03 1.53E+03 1.53E+03 1.53E+03 

ba139 1.04E-02 7.65E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 2.37E+01 2.27E+01 1.80E-01 5.81E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce140 1.40E+03 1.40E+03 1.43E+03 1.43E+03 1.43E+03 1.43E+03 1.43E+03 1.43E+03 

ce141 5.77E+01 5.68E+01 8.52E+00 2.42E-02 7.31E-16 9.20E-33 0.00E+00 0.00E+00 

ce142 1.32E+03 1.32E+03 1.32E+03 1.32E+03 1.32E+03 1.32E+03 1.32E+03 1.32E+03 

ce143 2.07E+00 1.39E+00 4.78E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 3.93E+02 3.92E+02 3.16E+02 1.62E+02 4.63E+00 5.47E-02 2.05E-17 0.00E+00 

cm242 1.77E+01 1.77E+01 1.21E+01 3.76E+00 8.91E-03 1.33E-03 1.09E-03 8.52E-04 

cm243 4.11E-01 4.11E-01 4.09E-01 4.02E-01 3.65E-01 3.24E-01 1.25E-01 3.80E-02 
B-17

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

cm244 4.66E+01 4.66E+01 4.62E+01 4.48E+01 3.85E+01 3.18E+01 6.88E+00 1.02E+00 

cm245 2.92E+00 2.92E+00 2.92E+00 2.92E+00 2.92E+00 2.91E+00 2.90E+00 2.89E+00 

cs133 1.30E+03 1.30E+03 1.32E+03 1.32E+03 1.32E+03 1.32E+03 1.32E+03 1.32E+03 

cs134 1.58E+02 1.58E+02 1.45E+02 1.13E+02 2.95E+01 5.51E+00 8.22E-06 4.28E-13 

cs136 6.99E-01 6.71E-01 6.18E-03 3.16E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 1.43E+03 1.43E+03 1.42E+03 1.39E+03 1.27E+03 1.13E+03 4.51E+02 1.43E+02 

eu151 1.27E-02 1.30E-02 3.76E-02 1.14E-01 5.10E-01 9.88E-01 4.22E+00 7.08E+00 

eu153 1.38E+02 1.38E+02 1.39E+02 1.39E+02 1.39E+02 1.39E+02 1.39E+02 1.39E+02 

eu154 3.02E+01 3.02E+01 2.96E+01 2.79E+01 2.02E+01 1.35E+01 5.39E-01 9.61E-03 

eu155 9.69E+00 9.68E+00 9.34E+00 8.37E+00 4.67E+00 2.26E+00 6.63E-03 4.54E-06 

gd155 6.91E-02 7.21E-02 4.10E-01 1.38E+00 5.08E+00 7.50E+00 9.75E+00 9.75E+00 

i131 8.36E+00 7.89E+00 3.72E-03 1.80E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 1.41E-01 1.18E-01 5.15E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.61E+00 8.53E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 4.89E-03 1.93E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 3.36E-01 4.52E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 2.96E+01 2.96E+01 2.91E+01 2.78E+01 2.15E+01 1.56E+01 1.18E+00 4.73E-02 

kr85m 1.35E-02 7.14E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 1.08E-03 3.43E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 1.43E-02 1.38E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la139 1.43E+03 1.43E+03 1.43E+03 1.43E+03 1.43E+03 1.43E+03 1.43E+03 1.43E+03 

la140 3.25E+00 3.20E+00 2.73E-02 8.80E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 1.31E-01 4.54E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.25E-02 2.14E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo100 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 1.10E+03 

mo95 7.68E+02 7.69E+02 8.30E+02 8.82E+02 8.85E+02 8.85E+02 8.85E+02 8.85E+02 

mo97 9.50E+02 9.51E+02 9.51E+02 9.51E+02 9.51E+02 9.51E+02 9.51E+02 9.51E+02 

mo98 9.74E+02 9.74E+02 9.74E+02 9.74E+02 9.74E+02 9.74E+02 9.74E+02 9.74E+02 

mo99 3.77E+00 3.09E+00 5.54E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb93m 5.72E-04 5.73E-04 6.56E-04 9.07E-04 2.11E-03 3.35E-03 7.61E-03 8.43E-03 

nb95 4.10E+01 4.10E+01 2.59E+01 1.71E+00 2.39E-07 6.30E-16 0.00E+00 0.00E+00 

nb97 5.49E-02 2.35E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
B-18

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

nb97m 6.62E-04 3.02E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd143 9.02E+02 9.03E+02 9.26E+02 9.26E+02 9.26E+02 9.26E+02 9.26E+02 9.26E+02 

nd144 1.16E+03 1.16E+03 1.24E+03 1.39E+03 1.55E+03 1.55E+03 1.55E+03 1.55E+03 

nd145 7.75E+02 7.76E+02 7.76E+02 7.76E+02 7.76E+02 7.76E+02 7.76E+02 7.76E+02 

nd147 8.03E+00 7.64E+00 2.77E-02 8.01E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd148 4.37E+02 4.37E+02 4.37E+02 4.37E+02 4.37E+02 4.37E+02 4.37E+02 4.37E+02 

np237 5.13E+02 5.14E+02 5.24E+02 5.24E+02 5.26E+02 5.30E+02 6.00E+02 7.09E+02 

np239 9.39E+01 7.44E+01 1.19E-04 1.19E-04 1.19E-04 1.19E-04 1.18E-04 1.18E-04 

pm147 2.04E+02 2.05E+02 1.99E+02 1.63E+02 5.68E+01 1.52E+01 3.93E-04 7.25E-10 

pr141 1.25E+03 1.25E+03 1.30E+03 1.31E+03 1.31E+03 1.31E+03 1.31E+03 1.31E+03 

pr143 2.24E+01 2.22E+01 2.51E-01 2.00E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.65E-02 1.65E-02 1.33E-02 6.81E-03 1.95E-04 2.30E-06 8.63E-22 0.00E+00 

pr144m 6.58E-05 6.57E-05 5.29E-05 2.71E-05 7.77E-07 9.16E-09 3.43E-24 0.00E+00 

pu238 1.87E+02 1.87E+02 1.94E+02 2.01E+02 1.98E+02 1.90E+02 1.39E+02 9.37E+01 

pu239 5.93E+03 5.95E+03 6.02E+03 6.02E+03 6.02E+03 6.02E+03 6.01E+03 6.01E+03 

pu240 2.57E+03 2.57E+03 2.57E+03 2.57E+03 2.57E+03 2.58E+03 2.59E+03 2.58E+03 

pu241 1.52E+03 1.52E+03 1.51E+03 1.45E+03 1.20E+03 9.39E+02 1.35E+02 1.20E+01 

pu242 6.05E+02 6.05E+02 6.05E+02 6.05E+02 6.05E+02 6.05E+02 6.05E+02 6.05E+02 

rb86 2.85E-02 2.76E-02 1.01E-03 3.63E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.66E-03 1.60E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103 5.05E+02 5.05E+02 5.47E+02 5.58E+02 5.58E+02 5.58E+02 5.58E+02 5.58E+02 

rh103m 5.26E-02 5.19E-02 1.08E-02 8.38E-05 5.30E-16 5.33E-30 0.00E+00 0.00E+00 

rh105 1.32E+00 9.78E-01 6.42E-19 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 1.79E-04 1.79E-04 1.51E-04 9.07E-05 5.96E-06 1.99E-07 2.99E-19 5.00E-34 

ru101 9.15E+02 9.15E+02 9.15E+02 9.15E+02 9.15E+02 9.15E+02 9.15E+02 9.15E+02 

ru103 5.36E+01 5.28E+01 1.10E+01 8.53E-02 5.40E-13 5.42E-27 0.00E+00 0.00E+00 

ru105 9.06E-02 4.66E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 1.91E+02 1.91E+02 1.62E+02 9.69E+01 6.37E+00 2.12E-01 3.20E-13 5.34E-28 

sb125 1.06E+01 1.06E+01 1.00E+01 8.29E+00 3.04E+00 8.65E-01 3.76E-05 1.33E-10 

sm147 8.52E+01 8.54E+01 9.85E+01 1.35E+02 2.41E+02 2.83E+02 2.98E+02 2.98E+02 

sm149 2.48E+00 2.78E+00 3.84E+00 3.84E+00 3.84E+00 3.84E+00 3.84E+00 3.84E+00 

sm150 3.44E+02 3.44E+02 3.44E+02 3.44E+02 3.44E+02 3.44E+02 3.44E+02 3.44E+02 
B-19

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

sm151 1.29E+01 1.30E+01 1.31E+01 1.31E+01 1.27E+01 1.22E+01 8.96E+00 6.10E+00 

sm152 1.19E+02 1.19E+02 1.19E+02 1.19E+02 1.19E+02 1.19E+02 1.19E+02 1.19E+02 

sr89 2.90E+01 2.86E+01 8.45E+00 1.94E-01 3.90E-10 5.23E-21 0.00E+00 0.00E+00 

sr90 6.25E+02 6.25E+02 6.21E+02 6.10E+02 5.54E+02 4.91E+02 1.88E+02 5.63E+01 

sr91 2.12E-01 5.40E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 2.66E-02 2.05E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99 9.36E+02 9.37E+02 9.40E+02 9.40E+02 9.40E+02 9.40E+02 9.40E+02 9.40E+02 

tc99m 3.17E-01 2.70E-01 4.88E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te125m 1.28E-01 1.28E-01 1.33E-01 1.15E-01 4.24E-02 1.21E-02 5.24E-07 1.85E-12 

te127 3.65E-02 3.36E-02 1.65E-03 2.86E-04 2.66E-08 2.42E-13 0.00E+00 0.00E+00 

te127m 7.66E-01 7.71E-01 4.70E-01 8.18E-02 7.59E-06 6.92E-11 0.00E+00 0.00E+00 

te129 9.22E-03 1.90E-03 2.40E-04 8.25E-07 6.85E-20 0.00E+00 0.00E+00 0.00E+00 

te129m 1.68E+00 1.66E+00 2.64E-01 9.08E-04 7.55E-17 3.37E-33 0.00E+00 0.00E+00 

te131 8.78E-04 5.75E-04 2.64E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 2.60E-01 1.75E-01 8.02E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 4.57E+00 3.85E+00 1.67E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

u234 1.77E+02 1.77E+02 1.78E+02 1.79E+02 1.85E+02 1.93E+02 2.43E+02 2.88E+02 

u235 8.46E+03 8.46E+03 8.46E+03 8.46E+03 8.46E+03 8.46E+03 8.47E+03 8.48E+03 

u236 4.78E+03 4.78E+03 4.78E+03 4.78E+03 4.78E+03 4.78E+03 4.79E+03 4.80E+03 

u238 9.35E+05 9.35E+05 9.35E+05 9.35E+05 9.35E+05 9.35E+05 9.35E+05 9.35E+05 

xe132 1.30E+03 1.30E+03 1.31E+03 1.31E+03 1.31E+03 1.31E+03 1.31E+03 1.31E+03 

xe133 1.12E+01 1.08E+01 9.40E-05 1.53E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe134 1.79E+03 1.79E+03 1.79E+03 1.79E+03 1.79E+03 1.79E+03 1.79E+03 1.79E+03 

xe135 3.27E-01 1.99E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 2.24E-03 3.01E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe136 2.75E+03 2.75E+03 2.75E+03 2.75E+03 2.75E+03 2.75E+03 2.75E+03 2.75E+03 

y90 1.66E-01 1.64E-01 1.58E-01 1.55E-01 1.41E-01 1.25E-01 4.76E-02 1.43E-02 

y91 4.55E+01 4.52E+01 1.58E+01 6.07E-01 1.87E-08 7.62E-18 0.00E+00 0.00E+00 

y91m 1.17E-02 2.99E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 8.68E-02 3.96E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 3.04E-01 8.34E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr93 8.30E+02 8.31E+02 8.31E+02 8.31E+02 8.31E+02 8.31E+02 8.31E+02 8.31E+02 
B-20

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

zr95 7.53E+01 7.47E+01 2.85E+01 1.45E+00 1.99E-07 5.22E-16 0.00E+00 0.00E+00 

zr97 7.15E-01 3.26E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 

Subtotal 98.8% 98.8% 98.8% 98.8% 98.8% 98.8% 98.7% 98.7% 

Table B.14. Nuclide mass (gram/MTU) for PWR-3 (47 GWd/MTU)

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

ag109 1.07E+02 1.07E+02 1.07E+02 1.07E+02 1.07E+02 1.07E+02 1.07E+02 1.07E+02 

am241 5.93E+01 5.95E+01 7.97E+01 1.41E+02 4.29E+02 7.16E+02 1.55E+03 1.56E+03 

am242 1.28E-01 5.61E-02 9.03E-06 8.99E-06 8.82E-06 8.60E-06 7.07E-06 5.53E-06 

am242m 7.00E-01 7.00E-01 7.00E-01 6.97E-01 6.83E-01 6.67E-01 5.48E-01 4.29E-01 

am243 1.87E+02 1.87E+02 1.87E+02 1.87E+02 1.87E+02 1.87E+02 1.87E+02 1.86E+02 

ba137 7.27E+01 7.27E+01 8.23E+01 1.12E+02 2.58E+02 4.24E+02 1.24E+03 1.61E+03 

ba137m 2.61E-04 2.61E-04 2.59E-04 2.55E-04 2.32E-04 2.07E-04 8.24E-05 2.61E-05 

ba138 1.85E+03 1.85E+03 1.85E+03 1.85E+03 1.85E+03 1.85E+03 1.85E+03 1.85E+03 

ba139 1.04E-02 7.64E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 2.37E+01 2.27E+01 1.80E-01 5.80E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce140 1.70E+03 1.70E+03 1.73E+03 1.73E+03 1.73E+03 1.73E+03 1.73E+03 1.73E+03 

ce141 5.76E+01 5.67E+01 8.50E+00 2.42E-02 7.30E-16 9.19E-33 0.00E+00 0.00E+00 

ce142 1.60E+03 1.60E+03 1.60E+03 1.60E+03 1.60E+03 1.60E+03 1.60E+03 1.60E+03 

ce143 2.06E+00 1.39E+00 4.78E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 4.08E+02 4.07E+02 3.28E+02 1.68E+02 4.81E+00 5.68E-02 2.13E-17 0.00E+00 

cm242 2.30E+01 2.30E+01 1.58E+01 4.90E+00 1.16E-02 1.74E-03 1.43E-03 1.12E-03 

cm243 6.08E-01 6.08E-01 6.05E-01 5.94E-01 5.40E-01 4.79E-01 1.85E-01 5.63E-02 

cm244 7.33E+01 7.33E+01 7.26E+01 7.05E+01 6.05E+01 5.00E+01 1.08E+01 1.60E+00 

cm245 5.20E+00 5.20E+00 5.20E+00 5.20E+00 5.20E+00 5.20E+00 5.18E+00 5.16E+00 

cs133 1.53E+03 1.54E+03 1.55E+03 1.55E+03 1.55E+03 1.55E+03 1.55E+03 1.55E+03 

cs134 2.03E+02 2.03E+02 1.87E+02 1.45E+02 3.80E+01 7.10E+00 1.06E-05 5.52E-13 

cs136 8.63E-01 8.27E-01 7.62E-03 3.90E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 1.71E+03 1.71E+03 1.70E+03 1.67E+03 1.52E+03 1.36E+03 5.39E+02 1.71E+02 

eu151 1.59E-02 1.61E-02 4.46E-02 1.32E-01 5.89E-01 1.14E+00 4.87E+00 8.17E+00 
B-21

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

eu153 1.64E+02 1.64E+02 1.65E+02 1.65E+02 1.65E+02 1.65E+02 1.65E+02 1.65E+02 

eu154 3.86E+01 3.86E+01 3.79E+01 3.57E+01 2.58E+01 1.73E+01 6.89E-01 1.23E-02 

eu155 1.19E+01 1.19E+01 1.15E+01 1.03E+01 5.76E+00 2.78E+00 8.17E-03 5.59E-06 

gd155 9.75E-02 1.01E-01 5.18E-01 1.72E+00 6.27E+00 9.25E+00 1.20E+01 1.20E+01 

i131 8.35E+00 7.88E+00 3.71E-03 1.79E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 1.41E-01 1.18E-01 5.14E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.60E+00 8.52E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 4.88E-03 1.93E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 3.35E-01 4.52E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 3.51E+01 3.51E+01 3.46E+01 3.30E+01 2.55E+01 1.85E+01 1.40E+00 5.61E-02 

kr85m 1.35E-02 7.11E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 1.08E-03 3.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 1.42E-02 1.37E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la139 1.73E+03 1.73E+03 1.73E+03 1.73E+03 1.73E+03 1.73E+03 1.73E+03 1.73E+03 

la140 3.26E+00 3.20E+00 2.72E-02 8.79E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 1.31E-01 4.53E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.25E-02 2.13E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo100 1.33E+03 1.33E+03 1.33E+03 1.33E+03 1.33E+03 1.33E+03 1.33E+03 1.33E+03 

mo95 9.41E+02 9.42E+02 1.00E+03 1.05E+03 1.06E+03 1.06E+03 1.06E+03 1.06E+03 

mo97 1.14E+03 1.14E+03 1.15E+03 1.15E+03 1.15E+03 1.15E+03 1.15E+03 1.15E+03 

mo98 1.17E+03 1.17E+03 1.17E+03 1.17E+03 1.17E+03 1.17E+03 1.17E+03 1.17E+03 

mo99 3.77E+00 3.09E+00 5.54E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb93m 8.13E-04 8.14E-04 9.13E-04 1.21E-03 2.65E-03 4.12E-03 9.19E-03 1.02E-02 

nb95 4.12E+01 4.12E+01 2.60E+01 1.71E+00 2.39E-07 6.30E-16 0.00E+00 0.00E+00 

nb97 5.48E-02 2.34E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 6.61E-04 3.01E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd143 1.06E+03 1.06E+03 1.09E+03 1.09E+03 1.09E+03 1.09E+03 1.09E+03 1.09E+03 

nd144 1.50E+03 1.50E+03 1.58E+03 1.74E+03 1.90E+03 1.91E+03 1.91E+03 1.91E+03 

nd145 9.19E+02 9.19E+02 9.19E+02 9.19E+02 9.19E+02 9.19E+02 9.19E+02 9.19E+02 

nd147 8.05E+00 7.66E+00 2.78E-02 8.02E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd148 5.25E+02 5.25E+02 5.25E+02 5.25E+02 5.25E+02 5.25E+02 5.25E+02 5.25E+02 

np237 6.60E+02 6.61E+02 6.72E+02 6.73E+02 6.74E+02 6.79E+02 7.59E+02 8.83E+02 
B-22

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

np239 9.17E+01 7.26E+01 1.61E-04 1.61E-04 1.61E-04 1.61E-04 1.61E-04 1.60E-04 

pm147 2.21E+02 2.21E+02 2.15E+02 1.76E+02 6.12E+01 1.64E+01 4.23E-04 7.82E-10 

pr141 1.52E+03 1.52E+03 1.57E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 

pr143 2.23E+01 2.21E+01 2.51E-01 1.99E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.72E-02 1.72E-02 1.38E-02 7.07E-03 2.03E-04 2.39E-06 8.96E-22 0.00E+00 

pr144m 6.83E-05 6.82E-05 5.49E-05 2.81E-05 8.07E-07 9.51E-09 3.57E-24 0.00E+00 

pu238 2.73E+02 2.74E+02 2.82E+02 2.91E+02 2.87E+02 2.75E+02 2.01E+02 1.35E+02 

pu239 6.31E+03 6.33E+03 6.40E+03 6.40E+03 6.40E+03 6.40E+03 6.39E+03 6.38E+03 

pu240 2.81E+03 2.81E+03 2.81E+03 2.81E+03 2.82E+03 2.83E+03 2.85E+03 2.85E+03 

pu241 1.73E+03 1.73E+03 1.71E+03 1.65E+03 1.36E+03 1.06E+03 1.53E+02 1.36E+01 

pu242 7.39E+02 7.39E+02 7.39E+02 7.39E+02 7.39E+02 7.39E+02 7.39E+02 7.39E+02 

rb86 3.45E-02 3.35E-02 1.22E-03 4.40E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.65E-03 1.59E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103 5.81E+02 5.82E+02 6.24E+02 6.35E+02 6.35E+02 6.35E+02 6.35E+02 6.35E+02 

rh103m 5.29E-02 5.21E-02 1.08E-02 8.41E-05 5.33E-16 5.35E-30 0.00E+00 0.00E+00 

rh105 1.34E+00 9.88E-01 6.49E-19 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 1.94E-04 1.94E-04 1.64E-04 9.83E-05 6.46E-06 2.15E-07 3.24E-19 5.42E-34 

ru101 1.09E+03 1.09E+03 1.09E+03 1.09E+03 1.09E+03 1.09E+03 1.09E+03 1.09E+03 

ru103 5.38E+01 5.31E+01 1.10E+01 8.57E-02 5.42E-13 5.45E-27 0.00E+00 0.00E+00 

ru105 9.10E-02 4.68E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 2.07E+02 2.07E+02 1.75E+02 1.05E+02 6.90E+00 2.30E-01 3.47E-13 5.79E-28 

sb125 1.19E+01 1.19E+01 1.13E+01 9.35E+00 3.43E+00 9.76E-01 4.24E-05 1.50E-10 

sm147 1.08E+02 1.08E+02 1.23E+02 1.61E+02 2.76E+02 3.21E+02 3.37E+02 3.37E+02 

sm149 2.74E+00 3.04E+00 4.11E+00 4.11E+00 4.11E+00 4.11E+00 4.11E+00 4.11E+00 

sm150 4.12E+02 4.12E+02 4.12E+02 4.12E+02 4.12E+02 4.12E+02 4.12E+02 4.12E+02 

sm151 1.49E+01 1.50E+01 1.52E+01 1.51E+01 1.46E+01 1.41E+01 1.03E+01 7.04E+00 

sm152 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 

sr89 2.88E+01 2.84E+01 8.39E+00 1.93E-01 3.87E-10 5.19E-21 0.00E+00 0.00E+00 

sr90 7.51E+02 7.51E+02 7.46E+02 7.33E+02 6.65E+02 5.90E+02 2.25E+02 6.77E+01 

sr91 2.11E-01 5.37E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 2.64E-02 2.04E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99 1.11E+03 1.11E+03 1.11E+03 1.11E+03 1.11E+03 1.11E+03 1.11E+03 1.11E+03 
B-23

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

tc99m 3.17E-01 2.70E-01 4.87E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te125m 1.47E-01 1.47E-01 1.50E-01 1.30E-01 4.78E-02 1.36E-02 5.92E-07 2.09E-12 

te127 3.65E-02 3.36E-02 1.71E-03 2.97E-04 2.76E-08 2.51E-13 0.00E+00 0.00E+00 

te127m 7.97E-01 8.01E-01 4.87E-01 8.48E-02 7.88E-06 7.18E-11 0.00E+00 0.00E+00 

te129 9.19E-03 1.90E-03 2.40E-04 8.24E-07 6.84E-20 0.00E+00 0.00E+00 0.00E+00 

te129m 1.68E+00 1.66E+00 2.64E-01 9.07E-04 7.54E-17 3.36E-33 0.00E+00 0.00E+00 

te131 8.73E-04 5.72E-04 2.62E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 2.58E-01 1.74E-01 7.97E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 4.56E+00 3.84E+00 1.67E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

u234 1.96E+02 1.96E+02 1.96E+02 1.98E+02 2.07E+02 2.18E+02 2.91E+02 3.55E+02 

u235 9.00E+03 9.00E+03 9.00E+03 9.00E+03 9.00E+03 9.00E+03 9.00E+03 9.01E+03 

u236 5.86E+03 5.86E+03 5.86E+03 5.86E+03 5.86E+03 5.86E+03 5.87E+03 5.89E+03 

u238 9.23E+05 9.23E+05 9.23E+05 9.23E+05 9.23E+05 9.23E+05 9.23E+05 9.23E+05 

xe132 1.60E+03 1.60E+03 1.60E+03 1.60E+03 1.60E+03 1.60E+03 1.60E+03 1.60E+03 

xe133 1.12E+01 1.08E+01 9.39E-05 1.53E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe134 2.16E+03 2.16E+03 2.16E+03 2.16E+03 2.16E+03 2.16E+03 2.16E+03 2.16E+03 

xe135 3.36E-01 2.01E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 2.24E-03 3.01E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe136 3.25E+03 3.25E+03 3.25E+03 3.25E+03 3.25E+03 3.25E+03 3.25E+03 3.25E+03 

y90 1.99E-01 1.97E-01 1.89E-01 1.86E-01 1.69E-01 1.50E-01 5.72E-02 1.72E-02 

y91 4.53E+01 4.50E+01 1.57E+01 6.04E-01 1.86E-08 7.59E-18 0.00E+00 0.00E+00 

y91m 1.17E-02 2.97E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 8.64E-02 3.94E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 3.03E-01 8.30E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr93 1.00E+03 1.00E+03 1.00E+03 1.00E+03 1.00E+03 1.00E+03 1.00E+03 1.00E+03 

zr95 7.53E+01 7.47E+01 2.85E+01 1.45E+00 1.99E-07 5.23E-16 0.00E+00 0.00E+00 

zr97 7.14E-01 3.25E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 

Subtotal 98.6% 98.6% 98.6% 98.5% 98.5% 98.5% 98.5% 98.4% 
B-24

Table B.15. Nuclide mass (gram/MTU) for PWR-Ext (72 GWd/MTU)

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

ag109 1.74E+02 1.74E+02 1.74E+02 1.74E+02 1.74E+02 1.74E+02 1.74E+02 1.74E+02 

am241 8.43E+01 8.45E+01 1.10E+02 1.87E+02 5.48E+02 9.08E+02 1.95E+03 1.96E+03 

am242 1.93E-01 8.46E-02 1.30E-05 1.30E-05 1.27E-05 1.24E-05 1.02E-05 7.99E-06 

am242m 1.01E+00 1.01E+00 1.01E+00 1.01E+00 9.87E-01 9.63E-01 7.91E-01 6.19E-01 

am243 4.70E+02 4.70E+02 4.70E+02 4.70E+02 4.70E+02 4.70E+02 4.68E+02 4.66E+02 

ba137 1.63E+02 1.63E+02 1.78E+02 2.21E+02 4.41E+02 6.89E+02 1.91E+03 2.46E+03 

ba137m 3.90E-04 3.90E-04 3.88E-04 3.82E-04 3.48E-04 3.10E-04 1.23E-04 3.90E-05 

ba138 2.80E+03 2.80E+03 2.80E+03 2.80E+03 2.80E+03 2.80E+03 2.80E+03 2.80E+03 

ba139 1.02E-02 7.46E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 2.30E+01 2.20E+01 1.75E-01 5.63E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce140 2.60E+03 2.60E+03 2.63E+03 2.63E+03 2.63E+03 2.63E+03 2.63E+03 2.63E+03 

ce141 5.58E+01 5.50E+01 8.24E+00 2.34E-02 7.07E-16 8.90E-33 0.00E+00 0.00E+00 

ce142 2.39E+03 2.39E+03 2.39E+03 2.39E+03 2.39E+03 2.39E+03 2.39E+03 2.39E+03 

ce143 1.97E+00 1.32E+00 4.55E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 4.06E+02 4.06E+02 3.27E+02 1.67E+02 4.79E+00 5.66E-02 2.12E-17 0.00E+00 

cm242 4.13E+01 4.13E+01 2.83E+01 8.79E+00 2.02E-02 2.52E-03 2.06E-03 1.61E-03 

cm243 1.55E+00 1.55E+00 1.54E+00 1.51E+00 1.37E+00 1.22E+00 4.71E-01 1.43E-01 

cm244 2.93E+02 2.93E+02 2.91E+02 2.82E+02 2.42E+02 2.00E+02 4.33E+01 6.40E+00 

cm245 2.69E+01 2.69E+01 2.69E+01 2.69E+01 2.68E+01 2.68E+01 2.68E+01 2.66E+01 

cs133 2.12E+03 2.12E+03 2.13E+03 2.13E+03 2.13E+03 2.13E+03 2.13E+03 2.13E+03 

cs134 3.74E+02 3.74E+02 3.44E+02 2.67E+02 6.99E+01 1.31E+01 1.95E-05 1.01E-12 

cs136 1.43E+00 1.37E+00 1.26E-02 6.45E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 2.56E+03 2.56E+03 2.54E+03 2.50E+03 2.28E+03 2.03E+03 8.08E+02 2.56E+02 

eu151 1.82E-02 1.85E-02 5.33E-02 1.61E-01 7.19E-01 1.39E+00 5.95E+00 9.99E+00 

eu153 2.40E+02 2.40E+02 2.41E+02 2.41E+02 2.41E+02 2.41E+02 2.41E+02 2.41E+02 

eu154 6.27E+01 6.27E+01 6.15E+01 5.78E+01 4.19E+01 2.80E+01 1.12E+00 1.99E-02 

eu155 1.93E+01 1.93E+01 1.86E+01 1.67E+01 9.29E+00 4.48E+00 1.32E-02 9.02E-06 

gd155 1.72E-01 1.78E-01 8.50E-01 2.78E+00 1.01E+01 1.49E+01 1.94E+01 1.94E+01 

i131 8.41E+00 7.94E+00 3.74E-03 1.81E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 1.41E-01 1.18E-01 5.14E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
B-25

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

i133 1.58E+00 8.41E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 4.72E-03 1.86E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 3.34E-01 4.49E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 4.73E+01 4.73E+01 4.66E+01 4.44E+01 3.43E+01 2.49E+01 1.89E+00 7.56E-02 

kr85m 1.17E-02 6.20E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 9.17E-04 2.90E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 1.20E-02 1.16E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la139 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 

la140 3.24E+00 3.16E+00 2.65E-02 8.54E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 1.27E-01 4.40E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.20E-02 2.05E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo100 2.02E+03 2.02E+03 2.02E+03 2.02E+03 2.02E+03 2.02E+03 2.02E+03 2.02E+03 

mo95 1.40E+03 1.40E+03 1.46E+03 1.50E+03 1.51E+03 1.51E+03 1.51E+03 1.51E+03 

mo97 1.72E+03 1.72E+03 1.72E+03 1.72E+03 1.72E+03 1.72E+03 1.72E+03 1.72E+03 

mo98 1.79E+03 1.79E+03 1.79E+03 1.79E+03 1.79E+03 1.79E+03 1.79E+03 1.79E+03 

mo99 3.74E+00 3.06E+00 5.49E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb93m 1.74E-03 1.75E-03 1.88E-03 2.30E-03 4.30E-03 6.36E-03 1.34E-02 1.48E-02 

nb95 3.88E+01 3.88E+01 2.44E+01 1.61E+00 2.25E-07 5.91E-16 0.00E+00 0.00E+00 

nb97 5.31E-02 2.27E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 6.41E-04 2.92E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd143 1.31E+03 1.32E+03 1.34E+03 1.34E+03 1.34E+03 1.34E+03 1.34E+03 1.34E+03 

nd144 2.71E+03 2.71E+03 2.79E+03 2.95E+03 3.11E+03 3.12E+03 3.12E+03 3.12E+03 

nd145 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 

nd147 7.97E+00 7.58E+00 2.75E-02 7.95E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd148 7.97E+02 7.97E+02 7.97E+02 7.97E+02 7.97E+02 7.97E+02 7.97E+02 7.97E+02 

np237 1.05E+03 1.05E+03 1.06E+03 1.06E+03 1.06E+03 1.07E+03 1.17E+03 1.33E+03 

np239 9.86E+01 7.81E+01 4.05E-04 4.05E-04 4.04E-04 4.04E-04 4.03E-04 4.01E-04 

pm147 2.27E+02 2.28E+02 2.21E+02 1.81E+02 6.29E+01 1.68E+01 4.35E-04 8.03E-10 

pr141 2.29E+03 2.29E+03 2.34E+03 2.35E+03 2.35E+03 2.35E+03 2.35E+03 2.35E+03 

pr143 2.13E+01 2.11E+01 2.39E-01 1.90E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.71E-02 1.71E-02 1.38E-02 7.05E-03 2.02E-04 2.38E-06 8.93E-22 0.00E+00 

pr144m 6.81E-05 6.79E-05 5.47E-05 2.80E-05 8.03E-07 9.48E-09 3.55E-24 0.00E+00 
B-26

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

pu238 6.38E+02 6.39E+02 6.53E+02 6.68E+02 6.56E+02 6.30E+02 4.60E+02 3.10E+02 

pu239 6.55E+03 6.57E+03 6.64E+03 6.64E+03 6.64E+03 6.64E+03 6.64E+03 6.63E+03 

pu240 3.53E+03 3.53E+03 3.54E+03 3.55E+03 3.58E+03 3.62E+03 3.76E+03 3.78E+03 

pu241 2.17E+03 2.17E+03 2.14E+03 2.06E+03 1.70E+03 1.33E+03 1.92E+02 1.71E+01 

pu242 1.42E+03 1.42E+03 1.42E+03 1.42E+03 1.42E+03 1.42E+03 1.42E+03 1.42E+03 

rb86 5.57E-02 5.41E-02 1.97E-03 7.11E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.39E-03 1.35E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103 7.63E+02 7.64E+02 8.10E+02 8.21E+02 8.21E+02 8.21E+02 8.21E+02 8.21E+02 

rh103m 5.70E-02 5.62E-02 1.17E-02 9.07E-05 5.74E-16 5.77E-30 0.00E+00 0.00E+00 

rh105 1.50E+00 1.11E+00 7.28E-19 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 2.60E-04 2.60E-04 2.20E-04 1.32E-04 8.66E-06 2.88E-07 4.35E-19 7.27E-34 

ru101 1.62E+03 1.62E+03 1.62E+03 1.62E+03 1.62E+03 1.62E+03 1.62E+03 1.62E+03 

ru103 5.80E+01 5.72E+01 1.19E+01 9.23E-02 5.85E-13 5.87E-27 0.00E+00 0.00E+00 

ru105 1.03E-01 5.29E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 2.78E+02 2.78E+02 2.35E+02 1.41E+02 9.26E+00 3.08E-01 4.65E-13 7.76E-28 

sb125 1.63E+01 1.63E+01 1.55E+01 1.28E+01 4.69E+00 1.34E+00 5.80E-05 2.05E-10 

sm147 1.52E+02 1.52E+02 1.67E+02 2.07E+02 3.24E+02 3.71E+02 3.87E+02 3.87E+02 

sm149 2.75E+00 3.07E+00 4.20E+00 4.20E+00 4.20E+00 4.20E+00 4.20E+00 4.20E+00 

sm150 6.19E+02 6.19E+02 6.19E+02 6.19E+02 6.19E+02 6.19E+02 6.19E+02 6.19E+02 

sm151 1.83E+01 1.84E+01 1.85E+01 1.84E+01 1.79E+01 1.72E+01 1.26E+01 8.60E+00 

sm152 1.66E+02 1.66E+02 1.66E+02 1.66E+02 1.66E+02 1.66E+02 1.66E+02 1.66E+02 

sr89 2.41E+01 2.39E+01 7.04E+00 1.62E-01 3.25E-10 4.36E-21 0.00E+00 0.00E+00 

sr90 1.04E+03 1.04E+03 1.04E+03 1.02E+03 9.24E+02 8.19E+02 3.13E+02 9.40E+01 

sr91 1.83E-01 4.65E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 2.35E-02 1.82E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 

tc99m 3.16E-01 2.68E-01 4.83E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te125m 2.07E-01 2.07E-01 2.08E-01 1.78E-01 6.54E-02 1.86E-02 8.10E-07 2.86E-12 

te127 3.88E-02 3.56E-02 1.75E-03 3.05E-04 2.83E-08 2.58E-13 0.00E+00 0.00E+00 

te127m 8.17E-01 8.21E-01 5.01E-01 8.71E-02 8.09E-06 7.38E-11 0.00E+00 0.00E+00 

te129 9.69E-03 2.00E-03 2.53E-04 8.69E-07 7.22E-20 0.00E+00 0.00E+00 0.00E+00 

te129m 1.77E+00 1.75E+00 2.79E-01 9.57E-04 7.95E-17 3.55E-33 0.00E+00 0.00E+00 
B-27

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

te131 9.04E-04 5.92E-04 2.72E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 2.68E-01 1.80E-01 8.26E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 4.56E+00 3.84E+00 1.67E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

u234 1.64E+02 1.64E+02 1.66E+02 1.69E+02 1.90E+02 2.15E+02 3.83E+02 5.30E+02 

u235 4.82E+03 4.82E+03 4.82E+03 4.82E+03 4.82E+03 4.82E+03 4.83E+03 4.84E+03 

u236 7.34E+03 7.34E+03 7.34E+03 7.34E+03 7.34E+03 7.34E+03 7.36E+03 7.38E+03 

u238 8.97E+05 8.97E+05 8.97E+05 8.97E+05 8.97E+05 8.97E+05 8.97E+05 8.97E+05 

xe132 2.63E+03 2.63E+03 2.64E+03 2.64E+03 2.64E+03 2.64E+03 2.64E+03 2.64E+03 

xe133 1.11E+01 1.07E+01 9.30E-05 1.51E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe134 3.27E+03 3.27E+03 3.27E+03 3.27E+03 3.27E+03 3.27E+03 3.27E+03 3.27E+03 

xe135 3.27E-01 1.99E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 2.22E-03 2.99E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe136 4.96E+03 4.96E+03 4.96E+03 4.96E+03 4.96E+03 4.96E+03 4.96E+03 4.96E+03 

y90 2.77E-01 2.75E-01 2.63E-01 2.58E-01 2.34E-01 2.08E-01 7.94E-02 2.38E-02 

y91 3.91E+01 3.89E+01 1.36E+01 5.22E-01 1.61E-08 6.56E-18 0.00E+00 0.00E+00 

y91m 1.01E-02 2.58E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 7.67E-02 3.50E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 2.76E-01 7.56E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr93 1.46E+03 1.46E+03 1.46E+03 1.46E+03 1.46E+03 1.46E+03 1.46E+03 1.46E+03 

zr95 7.07E+01 7.01E+01 2.68E+01 1.36E+00 1.86E-07 4.91E-16 0.00E+00 0.00E+00 

zr97 6.92E-01 3.15E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 

Subtotal 97.7% 97.7% 97.7% 97.7% 97.6% 97.6% 97.5% 97.5% 

C-1

APPENDIX C. MOX RESULTS

Table C. 1. Total activity (Ci/MTHM) for MOX fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

MOX-1 

(20GWd/MTHM) 6.92E+07 5.09E+07 6.36E+06 2.25E+06 5.79E+05 3.94E+05 1.05E+05 3.62E+0

MOX-2 

(40GWd/MTHM) 7.23E+07 5.38E+07 7.90E+06 3.25E+06 9.03E+05 6.18E+05 1.71E+05 5.68E+0

Table C.2. Total gamma heat (W/MTHM) for MOX fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

MOX-1 

(20GWd/MTHM) 1.56E+05 1.05E+05 9.66E+03 1.64E+03 3.68E+02 2.13E+02 7.17E+01 2.37E+0

MOX-2 

(40GWd/MTHM) 1.60E+05 1.10E+05 1.18E+04 3.11E+03 8.61E+02 4.60E+02 1.41E+02 4.56E+0

Table C.3. Total decay heat (W/MTHM) for MOX fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

MOX-1 

(20GWd/MTHM) 2.92E+05 1.93E+05 2.60E+04 9.09E+03 1.52E+03 1.05E+03 7.38E+02 5.62E+0

MOX-2 

(40GWd/MTHM) 3.05E+05 2.07E+05 3.44E+04 1.39E+04 2.51E+03 1.63E+03 1.01E+03 7.27E+0

Table C.4. Total photon emission (photon/s/MTHM) for MOX fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

MOX-1 

(20GWd/MTHM) 3.11E+18 2.24E+18 1.67E+17 5.03E+16 6.50E+15 3.29E+15 1.34E+15 6.14E+

MOX-2 

(40GWd/MTHM) 3.21E+18 2.34E+18 2.11E+17 7.84E+16 1.30E+16 6.59E+15 2.40E+15 1.01E+
C-2

Table C.5. Total neutron emission (neutron/s/MTHM) for MOX fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

MOX-1 

(20GWd/MTHM) 1.80E+09 1.80E+09 1.60E+09 1.27E+09 9.87E+08 8.20E+08 1.99E+08 5.13E+0

MOX-2 

(40GWd/MTHM) 2.87E+09 2.87E+09 2.50E+09 1.91E+09 1.44E+09 1.20E+09 2.94E+08 7.98E+0

Table C.6. Neutron flux (neutrons/cm2

-sec/MTHM) for MOX fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

MOX-1 

(20GWd/MTHM) 1.03E+05 1.03E+05 9.13E+04 7.29E+04 5.64E+04 4.69E+04 1.14E+04 2.93E+0

MOX-2 

(40GWd/MTHM) 1.64E+05 1.64E+05 1.43E+05 1.09E+05 8.24E+04 6.85E+04 1.68E+04 4.57E+0

Table C.7. Pu total (gram/MTHM) for MOX fuel

Group ID 5 hours 1 days 90 days 1 year 5 years 10 years 50 years

100 

years

MOX-1 

(20GWd/MTHM) 2.96E+04 2.96E+04 2.96E+04 2.95E+04 2.90E+04 2.84E+04 2.66E+04 2.62E+0

MOX-2 

(40GWd/MTHM) 2.99E+04 2.99E+04 2.99E+04 2.98E+04 2.91E+04 2.83E+04 2.59E+04 2.55E+0

Table C.8. Nuclide activity (Ci/MTHM) for MOX-1 (20 GWd/MTHM)

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

am241 4.73E+02 4.74E+02 6.08E+02 1.01E+03 2.92E+03 4.83E+03 1.03E+04 1.04E+04 

ba137m 6.20E+04 6.20E+04 6.16E+04 6.06E+04 5.52E+04 4.92E+04 1.96E+04 6.20E+03 

ba139 1.64E+05 1.21E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.67E+06 1.60E+06 1.27E+04 4.10E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce141 1.57E+06 1.55E+06 2.32E+05 6.60E+02 1.99E-11 2.51E-28 0.00E+00 0.00E+00 

ce143 1.27E+06 8.54E+05 2.95E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 8.28E+05 8.26E+05 6.65E+05 3.41E+05 9.77E+03 1.15E+02 4.32E-14 0.00E+00 

cm242 8.64E+04 8.64E+04 5.93E+04 1.84E+04 5.12E+01 1.39E+01 1.14E+01 8.94E+00 
C-3

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

cm244 8.49E+03 8.49E+03 8.42E+03 8.18E+03 7.02E+03 5.80E+03 1.26E+03 1.85E+02 

cs134 6.37E+04 6.37E+04 5.87E+04 4.56E+04 1.19E+04 2.23E+03 3.32E-03 1.73E-10 

cs136 4.45E+04 4.27E+04 3.93E+02 2.01E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 6.54E+04 6.54E+04 6.51E+04 6.40E+04 5.83E+04 5.20E+04 2.07E+04 6.54E+03 

i131 1.10E+06 1.04E+06 4.90E+02 2.37E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 1.51E+06 1.27E+06 5.50E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.83E+06 9.71E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 1.24E+05 4.84E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 1.19E+06 1.61E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 3.94E+03 3.94E+03 3.88E+03 3.70E+03 2.86E+03 2.07E+03 1.58E+02 6.29E+00 

kr85m 8.82E+04 4.66E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 2.34E+04 7.41E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 1.34E+05 1.30E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la140 1.71E+06 1.69E+06 1.46E+04 4.72E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 7.21E+05 2.50E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.74E+05 2.97E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo99 1.80E+06 1.47E+06 2.64E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb95 1.32E+06 1.32E+06 8.67E+05 5.80E+04 8.12E-03 2.14E-11 0.00E+00 0.00E+00 

nb97 1.43E+06 6.10E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 1.27E+06 5.77E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd147 6.34E+05 6.03E+05 2.19E+03 6.32E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

np239 1.89E+07 1.50E+07 6.41E+01 6.41E+01 6.41E+01 6.41E+01 6.38E+01 6.35E+01 

pr143 1.40E+06 1.38E+06 1.57E+04 1.25E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 8.28E+05 8.26E+05 6.65E+05 3.41E+05 9.77E+03 1.15E+02 4.32E-14 0.00E+00 

pr144m 7.90E+03 7.89E+03 6.35E+03 3.25E+03 9.33E+01 1.10E+00 4.12E-16 0.00E+00 

pu238 4.27E+03 4.28E+03 4.41E+03 4.59E+03 4.54E+03 4.36E+03 3.19E+03 2.15E+03 

pu239 1.06E+03 1.06E+03 1.07E+03 1.07E+03 1.06E+03 1.06E+03 1.06E+03 1.06E+03 

pu240 1.75E+03 1.75E+03 1.75E+03 1.75E+03 1.75E+03 1.75E+03 1.76E+03 1.75E+03 

pu241 3.47E+05 3.47E+05 3.43E+05 3.30E+05 2.72E+05 2.13E+05 3.07E+04 2.72E+03 

rb86 6.91E+02 6.71E+02 2.45E+01 8.82E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.50E+05 1.45E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103m 1.93E+06 1.90E+06 3.95E+05 3.07E+03 1.95E-08 1.96E-22 0.00E+00 0.00E+00 
C-4

Nuclides 5 hours 1 days 90 days 1 year 5 years 10 years 50 years 100 

years

rh105 1.43E+06 1.05E+06 6.92E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 7.27E+05 7.26E+05 6.15E+05 3.68E+05 2.42E+04 8.06E+02 1.22E-09 2.03E-24 

ru103 1.95E+06 1.93E+06 4.00E+05 3.11E+03 1.97E-08 1.98E-22 0.00E+00 0.00E+00 

ru105 7.52E+05 3.87E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 7.27E+05 7.26E+05 6.15E+05 3.68E+05 2.42E+04 8.06E+02 1.22E-09 2.03E-24 

sr89 5.89E+05 5.83E+05 1.72E+05 3.95E+03 7.93E-06 1.06E-16 0.00E+00 0.00E+00 

sr90 2.60E+04 2.60E+04 2.59E+04 2.54E+04 2.31E+04 2.05E+04 7.81E+03 2.35E+03 

sr91 6.00E+05 1.53E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 2.77E+05 2.14E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99m 1.66E+06 1.42E+06 2.56E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te127 1.19E+05 1.09E+05 6.86E+03 1.19E+03 1.11E-01 1.01E-06 0.00E+00 0.00E+00 

te127m 1.17E+04 1.17E+04 7.00E+03 1.22E+03 1.13E-01 1.03E-06 0.00E+00 0.00E+00 

te129 2.23E+05 4.59E+04 5.78E+03 1.99E+01 1.65E-12 0.00E+00 0.00E+00 0.00E+00 

te129m 5.83E+04 5.75E+04 9.17E+03 3.15E+01 2.62E-12 1.17E-28 0.00E+00 0.00E+00 

te131 5.92E+04 3.89E+04 1.79E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 2.21E+05 1.48E+05 6.80E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 1.46E+06 1.23E+06 5.33E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe133 2.12E+06 2.04E+06 1.77E+01 2.88E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135 1.11E+06 5.73E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 2.05E+05 2.76E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y90 2.66E+04 2.65E+04 2.59E+04 2.54E+04 2.31E+04 2.05E+04 7.82E+03 2.35E+03 

y91 8.16E+05 8.12E+05 2.83E+05 1.09E+04 3.36E-04 1.37E-13 0.00E+00 0.00E+00 

y91m 3.86E+05 9.83E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 6.93E+05 3.17E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 8.79E+05 2.41E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr95 1.40E+06 1.38E+06 5.28E+05 2.69E+04 3.68E-03 9.69E-12 0.00E+00 0.00E+00 

zr97 1.33E+06 6.07E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Totala 6.92E+07 5.09E+07 6.36E+06 2.25E+06 5.79E+05 3.94E+05 1.05E+05 3.62E+04 

Subtotalb 92.9% 95.3% 97.2% 94.2% 91.9% 96.4% 99.0% 98.9% 

a Total includes contributions from all actinides and fission products in the fuel. b Subtotal is the percent contribution of nuclides listed in the table to the total.
C-5

Table C.9. Nuclide activity (Ci/MTHM) for MOX-2 (40 GWd/MTHM)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

am241 6.71E+02 6.73E+02 8.53E+02 1.40E+03 3.97E+03 6.53E+03 1.39E+04 1.40E+04 

ba137m 1.22E+05 1.22E+05 1.21E+05 1.19E+05 1.09E+05 9.69E+04 3.86E+04 1.22E+04 

ba139 1.63E+05 1.20E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 1.65E+06 1.58E+06 1.25E+04 4.04E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce141 1.56E+06 1.54E+06 2.30E+05 6.54E+02 1.98E-11 2.49E-28 0.00E+00 0.00E+00 

ce143 1.24E+06 8.31E+05 2.87E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 1.05E+06 1.05E+06 8.44E+05 4.32E+05 1.24E+04 1.46E+02 5.48E-14 0.00E+00 

cm242 1.60E+05 1.60E+05 1.10E+05 3.40E+04 8.88E+01 2.01E+01 1.64E+01 1.29E+01 

cm244 1.24E+04 1.24E+04 1.22E+04 1.19E+04 1.02E+04 8.43E+03 1.83E+03 2.70E+02 

cs134 2.01E+05 2.00E+05 1.85E+05 1.43E+05 3.75E+04 7.01E+03 1.04E-02 5.44E-10 

cs136 7.70E+04 7.39E+04 6.80E+02 3.48E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 1.29E+05 1.29E+05 1.28E+05 1.26E+05 1.15E+05 1.02E+05 4.07E+04 1.29E+04 

i131 1.09E+06 1.03E+06 4.84E+02 2.34E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 1.50E+06 1.25E+06 5.44E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.81E+06 9.61E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 1.22E+05 4.80E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 1.19E+06 1.60E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 6.92E+03 6.92E+03 6.81E+03 6.49E+03 5.01E+03 3.63E+03 2.76E+02 1.10E+01 

kr85m 7.93E+04 4.19E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 2.08E+04 6.57E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 1.18E+05 1.14E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la140 1.70E+06 1.68E+06 1.44E+04 4.66E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 7.05E+05 2.45E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.70E+05 2.90E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo99 1.78E+06 1.46E+06 2.62E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb95 1.40E+06 1.40E+06 8.88E+05 5.87E+04 8.21E-03 2.16E-11 0.00E+00 0.00E+00 

nb97 1.39E+06 5.96E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 1.24E+06 5.64E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd147 6.32E+05 6.01E+05 2.18E+03 6.30E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

np239 1.97E+07 1.56E+07 6.54E+01 6.54E+01 6.54E+01 6.53E+01 6.51E+01 6.48E+01 
C-6

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

pr143 1.36E+06 1.35E+06 1.53E+04 1.21E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.05E+06 1.05E+06 8.44E+05 4.32E+05 1.24E+04 1.46E+02 5.48E-14 0.00E+00 

pr144m 1.00E+04 1.00E+04 8.05E+03 4.13E+03 1.18E+02 1.40E+00 5.23E-16 0.00E+00 

pu238 3.19E+03 3.19E+03 3.45E+03 3.81E+03 3.86E+03 3.71E+03 2.71E+03 1.83E+03 

pu239 8.76E+02 8.77E+02 8.82E+02 8.82E+02 8.81E+02 8.81E+02 8.80E+02 8.79E+02 

pu240 2.20E+03 2.20E+03 2.20E+03 2.20E+03 2.21E+03 2.21E+03 2.22E+03 2.21E+03 

pu241 4.67E+05 4.67E+05 4.61E+05 4.45E+05 3.66E+05 2.87E+05 4.14E+04 3.67E+03 

rb86 1.35E+03 1.31E+03 4.79E+01 1.72E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.32E+05 1.28E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103m 2.04E+06 2.01E+06 4.17E+05 3.24E+03 2.05E-08 2.06E-22 0.00E+00 0.00E+00 

rh105 1.51E+06 1.11E+06 7.29E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 1.09E+06 1.09E+06 9.20E+05 5.51E+05 3.62E+04 1.21E+03 1.82E-09 3.04E-24 

ru103 2.06E+06 2.03E+06 4.22E+05 3.28E+03 2.08E-08 2.08E-22 0.00E+00 0.00E+00 

ru105 7.96E+05 4.09E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 1.09E+06 1.09E+06 9.20E+05 5.51E+05 3.62E+04 1.21E+03 1.82E-09 3.04E-24 

sr89 5.39E+05 5.33E+05 1.57E+05 3.62E+03 7.25E-06 9.72E-17 0.00E+00 0.00E+00 

sr90 4.58E+04 4.58E+04 4.56E+04 4.47E+04 4.06E+04 3.60E+04 1.38E+04 4.13E+03 

sr91 5.40E+05 1.37E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 2.54E+05 1.97E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99m 1.65E+06 1.40E+06 2.54E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te127 1.17E+05 1.08E+05 6.77E+03 1.18E+03 1.09E-01 9.97E-07 0.00E+00 0.00E+00 

te127m 1.15E+04 1.15E+04 6.91E+03 1.20E+03 1.12E-01 1.02E-06 0.00E+00 0.00E+00 

te129 2.23E+05 4.63E+04 5.86E+03 2.01E+01 1.67E-12 0.00E+00 0.00E+00 0.00E+00 

te129m 5.90E+04 5.82E+04 9.28E+03 3.19E+01 2.65E-12 1.18E-28 0.00E+00 0.00E+00 

te131 5.72E+04 3.76E+04 1.72E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 2.13E+05 1.43E+05 6.57E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 1.44E+06 1.22E+06 5.28E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe133 2.10E+06 2.02E+06 1.75E+01 2.85E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135 1.05E+06 5.58E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 2.05E+05 2.75E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y90 4.71E+04 4.69E+04 4.56E+04 4.47E+04 4.06E+04 3.60E+04 1.38E+04 4.13E+03 

y91 7.73E+05 7.69E+05 2.68E+05 1.03E+04 3.18E-04 1.30E-13 0.00E+00 0.00E+00 
C-7

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

y91m 3.47E+05 8.84E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 6.36E+05 2.90E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 8.22E+05 2.25E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr95 1.41E+06 1.40E+06 5.34E+05 2.72E+04 3.72E-03 9.79E-12 0.00E+00 0.00E+00 

zr97 1.30E+06 5.93E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 7.23E+07 5.38E+07 7.90E+06 3.25E+06 9.03E+05 6.18E+05 1.71E+05 5.68E+04 

Subtotal 91.8% 94.4% 96.8% 94.2% 92.1% 96.1% 99.4% 99.1% 

Table C.10. Nuclide mass (gram/MTHM) for MOX-1 (20 GWd/MTHM)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

ag109 1.06E+02 1.06E+02 1.06E+02 1.06E+02 1.06E+02 1.06E+02 1.06E+02 1.06E+02 

am241 1.38E+02 1.38E+02 1.77E+02 2.95E+02 8.52E+02 1.41E+03 3.01E+03 3.03E+03 

am242 1.86E-01 8.16E-02 2.18E-05 2.17E-05 2.13E-05 2.08E-05 1.71E-05 1.34E-05 

am242m 1.69E+00 1.69E+00 1.69E+00 1.69E+00 1.65E+00 1.61E+00 1.32E+00 1.04E+00 

am243 3.21E+02 3.21E+02 3.21E+02 3.21E+02 3.21E+02 3.21E+02 3.20E+02 3.18E+02 

ba137 1.53E+01 1.54E+01 1.96E+01 3.25E+01 9.73E+01 1.70E+02 5.31E+02 6.94E+02 

ba137m 1.15E-04 1.15E-04 1.15E-04 1.13E-04 1.03E-04 9.15E-05 3.64E-05 1.15E-05 

ba138 7.37E+02 7.37E+02 7.37E+02 7.37E+02 7.37E+02 7.37E+02 7.37E+02 7.37E+02 

ba139 1.01E-02 7.41E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 2.29E+01 2.19E+01 1.74E-01 5.60E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce140 6.42E+02 6.43E+02 6.67E+02 6.68E+02 6.68E+02 6.68E+02 6.68E+02 6.68E+02 

ce141 5.52E+01 5.44E+01 8.15E+00 2.32E-02 6.99E-16 8.80E-33 0.00E+00 0.00E+00 

ce142 6.11E+02 6.11E+02 6.11E+02 6.11E+02 6.11E+02 6.11E+02 6.11E+02 6.11E+02 

ce143 1.92E+00 1.29E+00 4.44E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 2.60E+02 2.59E+02 2.09E+02 1.07E+02 3.07E+00 3.62E-02 1.36E-17 0.00E+00 

cm242 2.61E+01 2.61E+01 1.79E+01 5.56E+00 1.55E-02 4.21E-03 3.45E-03 2.70E-03 

cm243 4.29E-01 4.29E-01 4.27E-01 4.19E-01 3.81E-01 3.38E-01 1.31E-01 3.97E-02 

cm244 1.05E+02 1.05E+02 1.04E+02 1.01E+02 8.67E+01 7.16E+01 1.55E+01 2.29E+00 

cm245 6.97E+00 6.97E+00 6.97E+00 6.97E+00 6.96E+00 6.96E+00 6.94E+00 6.91E+00 

cs133 7.22E+02 7.23E+02 7.35E+02 7.35E+02 7.35E+02 7.35E+02 7.35E+02 7.35E+02 

cs134 4.93E+01 4.93E+01 4.54E+01 3.53E+01 9.21E+00 1.72E+00 2.57E-06 1.34E-13 
C-8

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

cs136 6.10E-01 5.85E-01 5.38E-03 2.76E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 7.54E+02 7.54E+02 7.50E+02 7.37E+02 6.72E+02 5.99E+02 2.38E+02 7.54E+01 

eu151 4.24E-02 4.28E-02 8.30E-02 2.07E-01 8.52E-01 1.63E+00 6.90E+00 1.16E+01 

eu153 8.13E+01 8.15E+01 8.21E+01 8.21E+01 8.21E+01 8.21E+01 8.21E+01 8.21E+01 

eu154 1.60E+01 1.60E+01 1.56E+01 1.47E+01 1.07E+01 7.13E+00 2.84E-01 5.07E-03 

eu155 5.50E+00 5.50E+00 5.31E+00 4.76E+00 2.66E+00 1.28E+00 3.77E-03 2.58E-06 

gd155 7.36E-02 7.53E-02 2.67E-01 8.19E-01 2.92E+00 4.29E+00 5.57E+00 5.58E+00 

i131 8.83E+00 8.34E+00 3.94E-03 1.91E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 1.46E-01 1.22E-01 5.31E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i133 1.61E+00 8.57E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 4.62E-03 1.81E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 3.38E-01 4.54E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 1.01E+01 1.01E+01 9.92E+00 9.45E+00 7.30E+00 5.29E+00 4.03E-01 1.61E-02 

kr85m 1.07E-02 5.66E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 8.26E-04 2.62E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 1.07E-02 1.03E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la139 6.88E+02 6.88E+02 6.88E+02 6.88E+02 6.88E+02 6.88E+02 6.88E+02 6.88E+02 

la140 3.07E+00 3.04E+00 2.63E-02 8.49E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 1.27E-01 4.41E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.20E-02 2.04E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo100 5.73E+02 5.73E+02 5.73E+02 5.73E+02 5.73E+02 5.73E+02 5.73E+02 5.73E+02 

mo95 2.95E+02 2.96E+02 3.47E+02 3.91E+02 3.94E+02 3.94E+02 3.94E+02 3.94E+02 

mo97 4.55E+02 4.55E+02 4.56E+02 4.56E+02 4.56E+02 4.56E+02 4.56E+02 4.56E+02 

mo98 4.86E+02 4.86E+02 4.86E+02 4.86E+02 4.86E+02 4.86E+02 4.86E+02 4.86E+02 

mo99 3.75E+00 3.07E+00 5.51E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb93m 1.24E-04 1.24E-04 1.57E-04 2.58E-04 7.40E-04 1.24E-03 2.94E-03 3.27E-03 

nb95 3.35E+01 3.36E+01 2.21E+01 1.48E+00 2.07E-07 5.44E-16 0.00E+00 0.00E+00 

nb97 5.30E-02 2.27E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 6.39E-04 2.91E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd143 4.93E+02 4.94E+02 5.16E+02 5.16E+02 5.16E+02 5.16E+02 5.16E+02 5.16E+02 

nd144 2.87E+02 2.88E+02 3.38E+02 4.40E+02 5.44E+02 5.47E+02 5.47E+02 5.47E+02 

nd145 3.73E+02 3.73E+02 3.73E+02 3.73E+02 3.73E+02 3.73E+02 3.73E+02 3.73E+02 
C-9

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

nd147 7.83E+00 7.45E+00 2.70E-02 7.81E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd148 2.20E+02 2.20E+02 2.20E+02 2.20E+02 2.20E+02 2.20E+02 2.20E+02 2.20E+02 

np237 1.10E+02 1.10E+02 1.13E+02 1.13E+02 1.17E+02 1.26E+02 2.82E+02 5.24E+02 

np239 8.15E+01 6.46E+01 2.76E-04 2.76E-04 2.76E-04 2.76E-04 2.75E-04 2.74E-04 

pm147 1.48E+02 1.48E+02 1.46E+02 1.20E+02 4.17E+01 1.11E+01 2.88E-04 5.32E-10 

pr141 5.78E+02 5.79E+02 6.25E+02 6.33E+02 6.33E+02 6.33E+02 6.33E+02 6.33E+02 

pr143 2.08E+01 2.06E+01 2.33E-01 1.85E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.10E-02 1.09E-02 8.80E-03 4.51E-03 1.29E-04 1.52E-06 5.71E-22 0.00E+00 

pr144m 4.36E-05 4.35E-05 3.50E-05 1.79E-05 5.14E-07 6.06E-09 2.27E-24 0.00E+00 

pu238 2.49E+02 2.50E+02 2.57E+02 2.68E+02 2.65E+02 2.55E+02 1.86E+02 1.25E+02 

pu239 1.71E+04 1.71E+04 1.72E+04 1.72E+04 1.72E+04 1.72E+04 1.71E+04 1.71E+04 

pu240 7.69E+03 7.69E+03 7.69E+03 7.69E+03 7.70E+03 7.72E+03 7.74E+03 7.71E+03 

pu241 3.34E+03 3.34E+03 3.30E+03 3.18E+03 2.62E+03 2.06E+03 2.96E+02 2.62E+01 

pu242 1.25E+03 1.25E+03 1.25E+03 1.25E+03 1.25E+03 1.25E+03 1.25E+03 1.25E+03 

rb86 8.48E-03 8.23E-03 3.00E-04 1.08E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.25E-03 1.20E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103 4.39E+02 4.40E+02 4.87E+02 4.99E+02 4.99E+02 4.99E+02 4.99E+02 4.99E+02 

rh103m 5.93E-02 5.85E-02 1.22E-02 9.45E-05 5.98E-16 6.01E-30 0.00E+00 0.00E+00 

rh105 1.69E+00 1.25E+00 8.19E-19 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 2.05E-04 2.05E-04 1.74E-04 1.04E-04 6.84E-06 2.28E-07 3.43E-19 5.74E-34 

ru101 5.08E+02 5.08E+02 5.08E+02 5.08E+02 5.08E+02 5.08E+02 5.08E+02 5.08E+02 

ru103 6.04E+01 5.96E+01 1.24E+01 9.62E-02 6.09E-13 6.12E-27 0.00E+00 0.00E+00 

ru105 1.12E-01 5.75E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 2.19E+02 2.19E+02 1.86E+02 1.11E+02 7.31E+00 2.43E-01 3.67E-13 6.13E-28 

sb125 8.99E+00 8.99E+00 8.57E+00 7.10E+00 2.60E+00 7.41E-01 3.22E-05 1.14E-10 

sm147 3.39E+01 3.40E+01 4.36E+01 7.00E+01 1.48E+02 1.79E+02 1.90E+02 1.90E+02 

sm149 4.67E+00 4.93E+00 5.86E+00 5.86E+00 5.86E+00 5.86E+00 5.86E+00 5.86E+00 

sm150 1.72E+02 1.72E+02 1.72E+02 1.72E+02 1.72E+02 1.72E+02 1.72E+02 1.72E+02 

sm151 2.12E+01 2.13E+01 2.14E+01 2.13E+01 2.07E+01 1.99E+01 1.46E+01 9.94E+00 

sm152 9.61E+01 9.61E+01 9.61E+01 9.61E+01 9.61E+01 9.61E+01 9.61E+01 9.61E+01 

sr89 2.03E+01 2.01E+01 5.92E+00 1.36E-01 2.73E-10 3.66E-21 0.00E+00 0.00E+00 

sr90 1.89E+02 1.89E+02 1.87E+02 1.84E+02 1.67E+02 1.48E+02 5.66E+01 1.70E+01 
C-10

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

sr91 1.68E-01 4.27E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 2.20E-02 1.70E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99 5.02E+02 5.03E+02 5.06E+02 5.06E+02 5.06E+02 5.06E+02 5.06E+02 5.06E+02 

tc99m 3.15E-01 2.69E-01 4.85E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te125m 1.03E-01 1.03E-01 1.11E-01 9.87E-02 3.63E-02 1.03E-02 4.49E-07 1.58E-12 

te127 4.50E-02 4.14E-02 2.60E-03 4.52E-04 4.20E-08 3.83E-13 0.00E+00 0.00E+00 

te127m 1.23E+00 1.24E+00 7.42E-01 1.29E-01 1.20E-05 1.09E-10 0.00E+00 0.00E+00 

te129 1.07E-02 2.19E-03 2.76E-04 9.49E-07 7.88E-20 0.00E+00 0.00E+00 0.00E+00 

te129m 1.93E+00 1.91E+00 3.04E-01 1.05E-03 8.68E-17 3.87E-33 0.00E+00 0.00E+00 

te131 1.03E-03 6.78E-04 3.11E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 3.07E-01 2.06E-01 9.45E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 4.72E+00 3.97E+00 1.73E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

u234 4.92E+01 4.93E+01 4.97E+01 5.13E+01 5.96E+01 6.97E+01 1.38E+02 1.97E+02 

u235 4.45E+03 4.45E+03 4.46E+03 4.46E+03 4.46E+03 4.46E+03 4.48E+03 4.50E+03 

u236 5.30E+02 5.30E+02 5.31E+02 5.31E+02 5.34E+02 5.38E+02 5.70E+02 6.11E+02 

u238 9.44E+05 9.44E+05 9.44E+05 9.44E+05 9.44E+05 9.44E+05 9.44E+05 9.44E+05 

xe132 6.57E+02 6.58E+02 6.62E+02 6.62E+02 6.62E+02 6.62E+02 6.62E+02 6.62E+02 

xe133 1.13E+01 1.09E+01 9.46E-05 1.54E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe134 8.90E+02 8.90E+02 8.90E+02 8.90E+02 8.90E+02 8.90E+02 8.90E+02 8.90E+02 

xe135 4.35E-01 2.26E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 2.25E-03 3.03E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe136 1.31E+03 1.31E+03 1.31E+03 1.31E+03 1.31E+03 1.31E+03 1.31E+03 1.31E+03 

y90 4.88E-02 4.86E-02 4.75E-02 4.67E-02 4.24E-02 3.76E-02 1.44E-02 4.31E-03 

y91 3.33E+01 3.31E+01 1.16E+01 4.44E-01 1.37E-08 5.58E-18 0.00E+00 0.00E+00 

y91m 9.27E-03 2.37E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 7.20E-02 3.29E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 2.66E-01 7.28E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr93 3.22E+02 3.23E+02 3.23E+02 3.23E+02 3.23E+02 3.23E+02 3.23E+02 3.23E+02 

zr95 6.50E+01 6.45E+01 2.46E+01 1.25E+00 1.72E-07 4.51E-16 0.00E+00 0.00E+00 

zr97 6.90E-01 3.14E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 

Subtotal 99.4% 99.4% 99.4% 99.4% 99.4% 99.3% 99.3% 99.3% 
C-11

Table C.11. Nuclide mass (gram/MTHM) for MOX-2 (40 GWd/MTHM)

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

ag109 1.98E+02 1.98E+02 1.99E+02 1.99E+02 1.99E+02 1.99E+02 1.99E+02 1.99E+02 

am241 1.96E+02 1.96E+02 2.49E+02 4.08E+02 1.16E+03 1.90E+03 4.06E+03 4.09E+03 

am242 2.87E-01 1.26E-01 3.14E-05 3.13E-05 3.07E-05 2.99E-05 2.46E-05 1.92E-05 

am242m 2.44E+00 2.44E+00 2.43E+00 2.42E+00 2.38E+00 2.32E+00 1.91E+00 1.49E+00 

am243 3.27E+02 3.28E+02 3.28E+02 3.28E+02 3.27E+02 3.27E+02 3.26E+02 3.24E+02 

ba137 5.54E+01 5.55E+01 6.38E+01 8.92E+01 2.17E+02 3.61E+02 1.07E+03 1.39E+03 

ba137m 2.27E-04 2.27E-04 2.26E-04 2.22E-04 2.02E-04 1.80E-04 7.17E-05 2.27E-05 

ba138 1.46E+03 1.46E+03 1.46E+03 1.46E+03 1.46E+03 1.46E+03 1.46E+03 1.46E+03 

ba139 9.98E-03 7.34E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ba140 2.26E+01 2.16E+01 1.71E-01 5.52E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce140 1.30E+03 1.30E+03 1.32E+03 1.32E+03 1.32E+03 1.32E+03 1.32E+03 1.32E+03 

ce141 5.47E+01 5.39E+01 8.08E+00 2.30E-02 6.93E-16 8.73E-33 0.00E+00 0.00E+00 

ce142 1.20E+03 1.20E+03 1.20E+03 1.20E+03 1.20E+03 1.20E+03 1.20E+03 1.20E+03 

ce143 1.87E+00 1.25E+00 4.32E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ce144 3.30E+02 3.29E+02 2.65E+02 1.36E+02 3.89E+00 4.59E-02 1.72E-17 0.00E+00 

cm242 4.82E+01 4.82E+01 3.31E+01 1.03E+01 2.68E-02 6.05E-03 4.96E-03 3.88E-03 

cm243 1.15E+00 1.15E+00 1.14E+00 1.12E+00 1.02E+00 9.03E-01 3.48E-01 1.06E-01 

cm244 1.53E+02 1.53E+02 1.51E+02 1.47E+02 1.26E+02 1.04E+02 2.26E+01 3.33E+00 

cm245 1.44E+01 1.44E+01 1.44E+01 1.44E+01 1.44E+01 1.44E+01 1.43E+01 1.43E+01 

cs133 1.35E+03 1.35E+03 1.37E+03 1.37E+03 1.37E+03 1.37E+03 1.37E+03 1.37E+03 

cs134 1.55E+02 1.55E+02 1.43E+02 1.11E+02 2.90E+01 5.42E+00 8.08E-06 4.21E-13 

cs136 1.06E+00 1.01E+00 9.32E-03 4.77E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

cs137 1.48E+03 1.48E+03 1.48E+03 1.45E+03 1.32E+03 1.18E+03 4.69E+02 1.48E+02 

eu151 3.98E-02 4.02E-02 8.45E-02 2.21E-01 9.31E-01 1.79E+00 7.58E+00 1.27E+01 

eu153 1.85E+02 1.85E+02 1.86E+02 1.86E+02 1.86E+02 1.86E+02 1.86E+02 1.86E+02 

eu154 5.05E+01 5.05E+01 4.95E+01 4.66E+01 3.38E+01 2.26E+01 9.01E-01 1.61E-02 

eu155 1.38E+01 1.38E+01 1.33E+01 1.19E+01 6.66E+00 3.22E+00 9.45E-03 6.47E-06 

gd155 1.85E-01 1.89E-01 6.71E-01 2.06E+00 7.33E+00 1.08E+01 1.40E+01 1.40E+01 

i131 8.74E+00 8.25E+00 3.90E-03 1.88E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i132 1.45E-01 1.21E-01 5.26E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
C-12

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

i133 1.60E+00 8.48E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i134 4.58E-03 1.80E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

i135 3.37E-01 4.53E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr85 1.77E+01 1.77E+01 1.74E+01 1.66E+01 1.28E+01 9.29E+00 7.07E-01 2.82E-02 

kr85m 9.63E-03 5.09E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr87 7.33E-04 2.32E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

kr88 9.43E-03 9.11E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la139 1.35E+03 1.35E+03 1.35E+03 1.35E+03 1.35E+03 1.35E+03 1.35E+03 1.35E+03 

la140 3.07E+00 3.02E+00 2.60E-02 8.37E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la141 1.24E-01 4.32E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

la142 1.17E-02 1.99E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

mo100 1.15E+03 1.15E+03 1.15E+03 1.15E+03 1.15E+03 1.15E+03 1.15E+03 1.15E+03 

mo95 6.44E+02 6.45E+02 6.98E+02 7.43E+02 7.46E+02 7.46E+02 7.46E+02 7.46E+02 

mo97 8.96E+02 8.96E+02 8.97E+02 8.97E+02 8.97E+02 8.97E+02 8.97E+02 8.97E+02 

mo98 9.72E+02 9.72E+02 9.72E+02 9.72E+02 9.72E+02 9.72E+02 9.72E+02 9.72E+02 

mo99 3.72E+00 3.04E+00 5.46E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb93m 4.21E-04 4.21E-04 4.82E-04 6.67E-04 1.56E-03 2.47E-03 5.61E-03 6.21E-03 

nb95 3.57E+01 3.57E+01 2.26E+01 1.49E+00 2.09E-07 5.50E-16 0.00E+00 0.00E+00 

nb97 5.18E-02 2.21E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nb97m 6.25E-04 2.85E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd143 8.88E+02 8.89E+02 9.10E+02 9.10E+02 9.10E+02 9.10E+02 9.10E+02 9.10E+02 

nd144 8.22E+02 8.22E+02 8.86E+02 1.02E+03 1.15E+03 1.15E+03 1.15E+03 1.15E+03 

nd145 6.89E+02 6.89E+02 6.89E+02 6.89E+02 6.89E+02 6.89E+02 6.89E+02 6.89E+02 

nd147 7.81E+00 7.43E+00 2.70E-02 7.79E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

nd148 4.35E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 

np237 1.56E+02 1.56E+02 1.59E+02 1.59E+02 1.64E+02 1.76E+02 3.88E+02 7.14E+02 

np239 8.49E+01 6.73E+01 2.82E-04 2.82E-04 2.82E-04 2.82E-04 2.81E-04 2.79E-04 

pm147 2.00E+02 2.00E+02 1.95E+02 1.60E+02 5.55E+01 1.48E+01 3.84E-04 7.09E-10 

pr141 1.19E+03 1.19E+03 1.23E+03 1.24E+03 1.24E+03 1.24E+03 1.24E+03 1.24E+03 

pr143 2.02E+01 2.00E+01 2.27E-01 1.80E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

pr144 1.39E-02 1.39E-02 1.12E-02 5.72E-03 1.64E-04 1.93E-06 7.24E-22 0.00E+00 

pr144m 5.52E-05 5.51E-05 4.44E-05 2.27E-05 6.52E-07 7.69E-09 2.88E-24 0.00E+00 
C-13

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

pu238 1.86E+02 1.86E+02 2.01E+02 2.23E+02 2.25E+02 2.17E+02 1.58E+02 1.07E+02 

pu239 1.41E+04 1.41E+04 1.42E+04 1.42E+04 1.42E+04 1.42E+04 1.42E+04 1.42E+04 

pu240 9.70E+03 9.70E+03 9.70E+03 9.70E+03 9.72E+03 9.73E+03 9.77E+03 9.74E+03 

pu241 4.49E+03 4.49E+03 4.44E+03 4.28E+03 3.53E+03 2.77E+03 3.98E+02 3.53E+01 

pu242 1.41E+03 1.41E+03 1.41E+03 1.41E+03 1.41E+03 1.41E+03 1.41E+03 1.41E+03 

rb86 1.66E-02 1.61E-02 5.87E-04 2.11E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rb88 1.10E-03 1.06E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh103 8.24E+02 8.25E+02 8.75E+02 8.88E+02 8.88E+02 8.88E+02 8.88E+02 8.88E+02 

rh103m 6.26E-02 6.17E-02 1.28E-02 9.96E-05 6.31E-16 6.34E-30 0.00E+00 0.00E+00 

rh105 1.78E+00 1.32E+00 8.63E-19 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

rh106 3.07E-04 3.07E-04 2.60E-04 1.56E-04 1.02E-05 3.41E-07 5.14E-19 8.58E-34 

ru101 9.95E+02 9.95E+02 9.95E+02 9.95E+02 9.95E+02 9.95E+02 9.95E+02 9.95E+02 

ru103 6.37E+01 6.28E+01 1.30E+01 1.01E-01 6.42E-13 6.45E-27 0.00E+00 0.00E+00 

ru105 1.18E-01 6.09E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

ru106 3.28E+02 3.28E+02 2.78E+02 1.66E+02 1.09E+01 3.64E-01 5.49E-13 9.17E-28 

sb125 1.59E+01 1.59E+01 1.50E+01 1.25E+01 4.56E+00 1.30E+00 5.64E-05 1.99E-10 

sm147 8.44E+01 8.46E+01 9.74E+01 1.33E+02 2.37E+02 2.77E+02 2.92E+02 2.92E+02 

sm149 4.51E+00 4.80E+00 5.83E+00 5.83E+00 5.83E+00 5.83E+00 5.83E+00 5.83E+00 

sm150 3.59E+02 3.59E+02 3.59E+02 3.59E+02 3.59E+02 3.59E+02 3.59E+02 3.59E+02 

sm151 2.33E+01 2.34E+01 2.36E+01 2.34E+01 2.27E+01 2.19E+01 1.61E+01 1.09E+01 

sm152 1.53E+02 1.53E+02 1.53E+02 1.53E+02 1.53E+02 1.53E+02 1.53E+02 1.53E+02 

sr89 1.85E+01 1.83E+01 5.41E+00 1.24E-01 2.50E-10 3.35E-21 0.00E+00 0.00E+00 

sr90 3.32E+02 3.32E+02 3.30E+02 3.24E+02 2.94E+02 2.61E+02 9.97E+01 2.99E+01 

sr91 1.51E-01 3.84E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

sr92 2.02E-02 1.56E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

tc99 9.47E+02 9.48E+02 9.51E+02 9.51E+02 9.51E+02 9.51E+02 9.51E+02 9.51E+02 

tc99m 3.13E-01 2.66E-01 4.81E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te125m 1.98E-01 1.98E-01 2.01E-01 1.73E-01 6.36E-02 1.81E-02 7.87E-07 2.78E-12 

te127 4.45E-02 4.09E-02 2.56E-03 4.46E-04 4.14E-08 3.78E-13 0.00E+00 0.00E+00 

te127m 1.22E+00 1.22E+00 7.32E-01 1.27E-01 1.18E-05 1.08E-10 0.00E+00 0.00E+00 

te129 1.07E-02 2.21E-03 2.80E-04 9.61E-07 7.98E-20 0.00E+00 0.00E+00 0.00E+00 

te129m 1.96E+00 1.93E+00 3.08E-01 1.06E-03 8.79E-17 3.92E-33 0.00E+00 0.00E+00 
C-14

Nuclides 5 hours 1 day 90 days 1 year 5 years 10 years 50 years 100 

years

te131 9.97E-04 6.55E-04 3.00E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te131m 2.96E-01 1.99E-01 9.13E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

te132 4.67E+00 3.94E+00 1.71E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

u234 1.52E+01 1.52E+01 1.56E+01 1.68E+01 2.39E+01 3.25E+01 9.02E+01 1.41E+02 

u235 1.03E+03 1.03E+03 1.03E+03 1.03E+03 1.03E+03 1.03E+03 1.05E+03 1.07E+03 

u236 2.79E+02 2.79E+02 2.80E+02 2.80E+02 2.84E+02 2.90E+02 3.30E+02 3.81E+02 

u238 9.27E+05 9.27E+05 9.27E+05 9.27E+05 9.27E+05 9.27E+05 9.27E+05 9.27E+05 

xe132 1.44E+03 1.44E+03 1.44E+03 1.44E+03 1.44E+03 1.44E+03 1.44E+03 1.44E+03 

xe133 1.12E+01 1.08E+01 9.37E-05 1.52E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe134 1.77E+03 1.77E+03 1.77E+03 1.77E+03 1.77E+03 1.77E+03 1.77E+03 1.77E+03 

xe135 4.11E-01 2.20E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe135m 2.24E-03 3.02E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

xe136 2.61E+03 2.61E+03 2.61E+03 2.61E+03 2.61E+03 2.61E+03 2.61E+03 2.61E+03 

y90 8.66E-02 8.62E-02 8.37E-02 8.22E-02 7.47E-02 6.62E-02 2.53E-02 7.59E-03 

y91 3.15E+01 3.13E+01 1.09E+01 4.20E-01 1.29E-08 5.28E-18 0.00E+00 0.00E+00 

y91m 8.34E-03 2.13E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y92 6.61E-02 3.02E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

y93 2.48E-01 6.80E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

zr93 6.12E+02 6.12E+02 6.12E+02 6.12E+02 6.12E+02 6.12E+02 6.12E+02 6.12E+02 

zr95 6.57E+01 6.52E+01 2.49E+01 1.27E+00 1.73E-07 4.56E-16 0.00E+00 0.00E+00 

zr97 6.75E-01 3.07E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 

Total 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 1.00E+06 

Subtotal 98.7% 98.7% 98.7% 98.7% 98.7% 98.6% 98.6% 98.6% 
D-1

APPENDIX D. ANALYSIS OF MAXIMUM ASSEMBLY DECAY HEAT

The decay heat power for the hottest assembly is required as input for maximum thermal 

analyses. The calculated decay heat powers presented in Section 5.3 and tabulated in 

Appendixes A, B, and C of this report were based on representative fuel parameters and 

irradiation conditions; for example, the irradiation histories used in those calculations are based 

on average assembly specific powers for PWR and BWR fuel derived from data in the GC-859 

US inventory database: 38 MW/MTU for PWR fuel, and 24 MW/MTU for BWR fuel. This 

appendix focuses on the hottest fuel assemblies (the ones with maximum decay heat powers), 

and it studies the assemblies with burnups from 60 GWd/MTU to the maximum burnup as found 

in the current US spent fuel inventory through 2013. Decay heat power depends not only on the 

assembly burnup and cooling time, but also on the specific power during irradiation, particularly 

for short cooling times of interest for postulated accident analyses. Therefore, the decay heat 

values presented elsewhere in this report are not applicable for thermal analyses involving the 

hottest assemblies.

Other parameters also influence the decay heat power, but to a lesser degree than burnup, 

cooling time, and specific power. These other parameters include the assembly design, 

enrichment, exposure to integral absorber rods, discrete absorber rods and control blades, 

operating history (outage length etc.) and operating conditions (temperatures, boron levels etc.). 

For cooling times less than ~40 years, these parameters have a relatively small impact on 

decay heat since decay heat is dominated by fission products which are far less sensitive to 

these parameters than the actinides which dominate at longer cooling times.

This appendix evaluates decay heat power for assemblies that have experienced higher specific 

powers during operation than the reference cases used in this report, and those assemblies are 

expected to have higher decay heat power. This illustrates the importance of the appropriate 

application of the data documented in this report.

ANALYSIS OF GC-859 ASSEMBLY DATA

The specific powers for all assemblies in the GC-859 database, averaged over all cycles an 

assembly resided in the reactor core, are shown in Figure D.1. The maximum specific powers 

observed for these assemblies are about 54 MW/MTU for PWRs and 35 MW/MTU for BWRs. 

These operating specific powers exceed the values used to calculate the reference decay heat 

values presented in this report by about 45% and will result in larger decay heat powers.

This analysis of GC-859 data yields the average specific power of each assembly over the 

irradiation lifetime. However, the maximum specific power in any cycle during the irradiation can 

exceed the average value. The maximum specific power may be required in calculations for 

assemblies that have not achieved their expected end-of-life burnup. This can occur during an 

unplanned full core offload or at decommissioning. The GC-859 database does not currently 

include cycle-specific assembly burnup or power for all assemblies. Therefore, further analysis 

was performed using more detailed plant operating data to assess variations in the assemblyspecific power during each cycle of operation to identify the highest (limiting) specific power for 

thermal analysis.
D-2

ADDITIONAL PLANT DATA

Detailed cycle operating data was reviewed from PWR plants representing 15 cycles of 

assembly data and more than 6,000 assembly-cycles of information. The distribution of specific 

power values in each cycle of operation is illustrated in Figure D.2. The maximum assemblyaverage specific power observed in any cycle of the PWR data available in this study was 62 

MW/MTU. This power is 1.15 (62/54) times the maximum power values in Figure D.1, and 1.63 

(62/38) times the 38 MW/MTU value used in the reference calculations in this report.

Figure D.1. Assembly-specific power (MW/MTU) for BWR (left) and PWR (right) 

assemblies from the US spent fuel inventory database GC-859. Values 

represent the average specific power of each assembly over the operating 

lifetime of the assembly. Outlier data points are likely attributed to errors in 

the database.
D-3

Figure D.2. Specific power distribution of PWR assemblies in each operating cycle for 15 

cycles of data (data below 33 MW/MTU are omitted).

The maximum specific power experienced by BWR assemblies was estimated from a limited set 

of operating data for more than 600 assemblies from a modern BWR plant using a 10 × 10 

assembly design. The maximum assembly specific power observed for this dataset was 39.1 

MW/MTU, which is 1.12 (39/35) times the maximum power values in Figure D.1 and 1.63 

(39/24) times the 24 MW/MTU value used in the reference calculations in this report.

The maximum and average specific power values are summarized in Table D.1. The maximum 

specific power factors relative to average values are similar for the PWR and BWR assemblies 

analyzed. Note that the maximum specific power in any cycle for BWR (C) was estimated using 

the same factor (C/B) as PWR, due to the limited set of BWR data. 

MAXIMUM DECAY HEAT POWER

The decay heat power of an assembly increases with increasing specific power of the assembly. 

This effect is much more pronounced at shorter cooling times. After ~5 years the decay heat 

power is relatively insensitive to the operating power and is primarily dependent on the burnup.

0

50

100

150

200

250

300

350

400

450

500

333435363738394041424344454647484950515253545556575859606162636465

More

Frequency

Assembly specific power in each cycle (MW/MTU)
D-4

Table D.1. Summary of assembly specific power values

Reactor Type

Average 

specific powera

(MW/MTU)

Maximum 

lifetime 

specific powera

(MW/MTU)

Maximum 

specific power 

in any cycle 

(MW/MTU) 

Maximum 

lifetime

specific power 

factor relative 

to average

Maximum 

specific power 

factor in any 

cycle relative 

to average

(A) (B) (C) (B/A) (C/A)

PWR 38 54 62 1.42 1.63

BWR 24 35 40b 1.46 1.67b

a Average specific power over the operating lifetime of the assemblies

b Factors adopted from PWR data

Calculations were performed to determine factors that can be applied to the decay heat power 

values tabulated in Appendix A and B to estimate the hottest assembly. ORIGEN calculations 

were performed for the reference PWR specific power of 38 MW/MTU and the maximum 

specific power of 62 MW/MTU. Similarly, calculations were performed for the reference BWRspecific power of 24 MW/MTU and the maximum power of 40 MW/MTU. These calculations 

were performed for an assembly with a burnup of 60 GWd/MTU and an initial enrichment of 

4.95 wt% 235U. The ratio of the decay heat value from a calculation using the maximum specific 

power to one using the average value represents a factor that can be applied to the decay heat 

powers tabulated in Appendixes A, B, and C to obtain data for the hottest assembly for thermal 

calculations. These scaling factors are listed in Table D.2. 

Table D.2. Scaling factors for the hottest assembly

Cooling 

time 

(years)

Decay heat 

factor for 

hottest 

PWR 

assembly

Decay heat 

factor for 

hottest 

BWR 

assembly

0 1.63 1.67

0.03 1.52 1.56

0.1 1.47 1.50

0.3 1.39 1.43

0.5 1.35 1.39

1 1.29 1.33

2 1.22 1.26

3 1.16 1.19

4 1.11 1.13

5 1.07 1.09

10 1.01 1.03

The results illustrate the importance of the assembly-specific power on decay heat at short 

cooling times (< 5 years) for estimating the hottest assemblies. Therefore, appropriate 

adjustments are needed if the results compiled in this report (Appendixes A, B, and C) are used 

in calculations involving the hottest assemblies, because those results were based on average 

operating conditions.




NUREG/CR-7227 US Commercial Spent Nuclear Fuel Assembly Characteristics: 1968-2013