NUREG/CR-5625 (ORNL-6698) - Oak Ridge National Laboratory

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LIST OF FIGURES 6.1 Diagrammatic illustration of operating history variations having same total burnup and cycle times ............. 30 6.2 Cooper Nuclear Station operating history ......................................................... 33 Page 6.3 Cooper Nuclear Station assembly CZ515 operating history ............................................ 34 6.4 Cooper Nuclear Station assembly CZ102 operating history ............................................ 34 vii NUREG/CR-5625
LIST OF TABLES Page 2.1 List of nuclides updated as a function of burnup in the SAS2H analyses .................................. 3 3.1 Point Beach Unit 2 PWR assembly description ..................................................... 5 3.2 Point Beach Unit 2 PWR operating history ........................................................ 6 3.3 Point Beach Unit 2 assembly burnups and powers ................................................... 6 3.4 Turkey Point Unit 3 PWR assembly description .................................................... 7 3.5 Turkey Point Unit 3 PWR operating history ....................................................... 8 3.6 Turkey Point Unit 3 assembly burnups and powers .................................................. 8 3.7 Cooper Nuclear Station BWR assembly description ................................................. 9 3.8 Cooper Nuclear Station BWR operating history ................................................... 10 3.9 Cooper Nuclear Station adjusted cycle burnups .................................................... 10 3.10 Cooper Nuclear Station assembly powers ........................................................ 10 3.11 Element contents from clad, structure, and water (for BWR) .......................................... 11 23 235 3.12 Uranium isotope dependence on X wt % U enrichment ........................................... 11 3.13 Point Beach PWR measured and computed decay heat rates .......................................... 11 3.14 Turkey Point PWR measured and computed decay heat rates ......................................... 13 3.15 Cooper Nuclear Station BWR measured and computed decay heat rates ................................. 13 3.16 Summary of decay heat rate comparisons ........................................................ 14 5.1 BWR spent fuel heat generation rates, watts per kilogram U, for specific power = 12 kW/kgU ................ 19 5.2 BWR spent fuel heat generation rates, watts per kilogram U, for specific power = 20 kW/kgU ................ 20 5.3 BWR spent fuel heat generation rates, watts per kilogram U, for specific power = 30 kW/kgU ................ 21 5.4 BWR enrichments for burnups in tables ......................................................... 21 5.5 PWR spent fuel heat generation rates, watts per kilogram U, for specific power = 18 kW/kgU ................ 22 5.6 PWR spent fuel heat generation rates, watts per kilogram U, for specific power = 28 kW/kgU ................ 23 5.7 PWR spent fuel heat generation rates, watts per kilogram U, for specific power = 40 kW/kgU ................ 24 5.8 PWR enrichments for burnups in tables ......................................................... 24 5.9 Enrichment factor parameter values for BWR assemblies ............................................ 27 5.10 Enrichment factor parameter values for PWR assemblies ............................................ 27 5.11 Parameter ranges for applicability of the proposed regulatory guide .................................... 28 6.1 Comparison of heat rates from operating history variations ........................................... 31 6.2 Evaluation of accuracy in table interpolations ..................................................... 36 6.3 Evaluation of heat rates after adjustments for extreme power history changes ............................. 37 6.4 Excess power adjustment of decay heat, in W/kgU, using Eq. (14) compared with actual SAS2H calculations as percentage differences ........................................................... 41 6.5 Evaluation of adjustments for decreased initial enrichments .......................................... 41 6.6 Evaluation of adjustments for increased initial enrichments .......................................... 43 6.7 Percentage fission-product yields for fissile isotopes ................................................ 44 6.8 Percentage standard deviations in data for dominant fission products and light elements .................... 47 6.9 Computed standard deviation in nuclides and their total heat rate at 1 year for typical BWR .................. 48 6.10 Computed standard deviation in nuclides and their total heat rate at 110 years for typical BWR ............... 49 6.11 Percentage standard deviation in fission-product and light-element heat rate applying Q, 8, and fission yield uncertainties ................................................................. 51 NUREG/CR-5625 viii
Page 1 and 2: NUREG/CR-5625 ORNL-6698 Computing A
Page 3 and 4: NUREG/CR-5625 iv
Page 5: CONTENTS (continued) Page 6.6.3 Err
Page 9 and 10: LIST OF TABLES (continued) Page D.1
Page 11 and 12: NUREG/CR-5625 xii
Page 13 and 14: 1 INTRODUCTION Heat is generated du
Page 15 and 16: 2 SOURCES OF DATA FOR COMPUTING HEA
Page 17 and 18: Comparisons Table 3.1 Point Beach U
Page 19 and 20: Comparisons Table 3.4 Turkey Point
Page 21 and 22: Comparisons Table 3.7 Cooper Nuclea
Page 23 and 24: Comparisons a Table 3.11 Element co
Page 25 and 26: Comparisons a Table 3.14 Turkey Poi
Page 27 and 28: Comparisons 4 HEAT RATE DATA COMPUT
Page 29 and 30: Procedure 5 PROPOSED REGULATORY GUI
Page 31 and 32: Procedure Table 5.1 BWR spent fuel
Page 33 and 34: Procedure Table 5.3. BWR spent fuel
Page 35 and 36: Procedure Table 5.6. PWR spent fuel
Page 37 and 38: Procedure Compute p tab , the heat
Page 39 and 40: Procedure Table 5.9 Enrichment fact
Page 41 and 42: 6 DISCUSSION OF THE PROPOSED PROCED
Page 43 and 44: Table 6.1 Comparison of heat rates
Page 45 and 46: Discussion Figure 6.2 Cooper Nuclea
Page 47 and 48: Discussion to sufficiently cover th
Page 49 and 50: Discussion 37 NUREG/CR-5625
Page 51 and 52: Discussion 39 NUREG/CR-5625
Page 53 and 54: Table 6.4. Excess power adjustment
Page 55 and 56: Discussion A large quantity of data
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F y y ' 1 y 3 j i'1 (f i y i F yi /
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Discussion Table 6.8 Percentage sta
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Discussion Table 6.10 Computed stan
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Discussion Table 6.11 Percentage st
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Discussion Table 6.13 Summary of cr
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This section deals with inaccuracie
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Discussion Table 6.16 Summary of pe
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7 THE LWRARC CODE The LWRARC (Light
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LWRARC Code 3. Fuel type - Select f
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LWRARC Code Table 7.2 PWR fuel asse
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8 SUMMARY Proper methods of storing
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9 REFERENCES 1. O. W. Hermann and R
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References 34. F. J. Sweeney and J.
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APPENDIX A DATA AND SAMPLE INPUT TO
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Appendix A Table A.3 Operating hist
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Appendix A ' ' ASSEMBLY AND CYCLE P
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Appendix A The following is the ent
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APPENDIX B SAMPLE CASE USING HEAT G
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APPENDIX C LWRARC CODE SAMPLE RESUL
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Appendix C ************************
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Appendix C ************************
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APPENDIX D ACTINIDE, FISSION PRODUC
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Appendix D 89 NUREG/CR-5625
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APPENDIX E PLOTS OF MAJOR DECAY HEA
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Appendix E 99 NUREG/CR-5625
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NUREG/CR-5625 ORNL-6698 INTERNAL DI
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107. D. A. Thomas, B&W Fuel Co., 10
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NUREG/CR-5625 (ORNL-6698) - Oak Ridge National Laboratory

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