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

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FOREWORD This report will provide technical support for major revisions proposed to the current U.S. Nuclear Regulatory Commission (NRC) decay heat rate guide entitled "Regulatory Guide 3.54, Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation." A proposed revised guide is now under development by the NRC staff. The proposed procedure applies computed results of the SAS2H/ORIGEN-S analyses sequence of the SCALE-4 system, a more recent version of the software than that used for the current guide. The calculated decay heat rate data base proposed here has a broader application and is designed to be easier to use than that in the current guide. This report is not a substitute for NRC regulation, and compliance is not required. The approaches and/or methods described in this document are provided for information only. Publication of this report does not necessarily constitute NRC approval or agreement with the information contained herein. Donald A. Cool, Chief Radiation Protection and Health Effects Branch Division of Regulatory Applications Office of Nuclear Regulatory Research xi NUREG/CR-5625
NUREG/CR-5625 xii
Page 1 and 2: NUREG/CR-5625 ORNL-6698 Computing A
Page 3 and 4: NUREG/CR-5625 iv
Page 5 and 6: CONTENTS (continued) Page 6.6.3 Err
Page 7 and 8: LIST OF TABLES Page 2.1 List of nuc
Page 9: LIST OF TABLES (continued) Page D.1
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
Page 57 and 58: F y y ' 1 y 3 j i'1 (f i y i F yi /
Page 59 and 60: 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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