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

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Procedure Table 5.7. PWR spent fuel heat generation rates, watts per kilogram U, for specific power = 40 kW/kgU Cooling time, years Fuel burnup, MWd/kgU 25 30 35 40 45 50 1.0 8.946 10.050 10.900 11.820 12.580 13.466 1.4 6.514 7.400 8.111 8.863 9.514 10.254 2.0 4.462 5.129 5.692 6.284 6.821 7.418 2.8 2.947 3.441 3.884 4.346 4.787 5.267 4.0 1.853 2.212 2.554 2.910 3.265 3.647 5.0 1.429 1.728 2.021 2.327 2.639 2.970 7.0 1.067 1.304 1.543 1.793 2.052 2.325 10.0 0.881 1.078 1.278 1.488 1.705 1.936 15.0 0.754 0.921 1.091 1.268 1.452 1.645 20.0 0.678 0.827 0.978 1.136 1.298 1.469 25.0 0.619 0.754 0.890 1.032 1.178 1.331 30.0 0.570 0.693 0.816 0.945 1.077 1.215 40.0 0.488 0.592 0.695 0.803 0.912 1.026 50.0 0.423 0.512 0.599 0.691 0.783 0.879 60.0 0.371 0.448 0.522 0.601 0.680 0.762 70.0 0.329 0.396 0.461 0.529 0.597 0.668 80.0 0.294 0.353 0.410 0.470 0.530 0.592 90.0 0.266 0.319 0.369 0.422 0.475 0.530 100.0 0.243 0.290 0.336 0.383 0.430 0.479 110.0 0.224 0.267 0.308 0.351 0.393 0.437 Table 5.8 PWR enrichments for burnups in tables Average initial Fuel burnup, enrichment, MWd/kgU wt % U-235 25 2.4 30 2.8 35 3.2 40 3.6 45 3.9 50 4.2 NUREG/CR-5625 24
Procedure Compute p tab , the heat generation rate, at P ave , B tot , and Tc , by proper interpolation between the tabulated values of heat rates at the parameter limits of Eqs. (5) through (7). A linear interpolation should be used between heat rates for either burnup or specific power interpolations. In computing the heat rate at T c , the interpolation should be logarithmic in heat rate and linear in cooling time. Specifically, the interpolation formulae for interpolating in specific power, burnup, and cooling time, respectively, are p ' p L % p H & p L P H & P L (P ave & P L ) , p ' p L % p H & p L B H & B L (B tot & B L ) , p ' p L exp ln(p H /p L ) T H & T L (T c & T L ) , (5) (6) (7) where p L and p H represent the tabulated or interpolated heat rates at the appropriate parameter limits corresponding to the L and H index. If applied in the sequence given above, Eq. (5) would need to be used four times to obtain p values that correspond to B L and B H at values of T and T . A mini-table of four p values at P L H ave is now available to interpolate on burnup and cooling time. Equation (6) would then be applied to obtain two values of p at T L and T H . One final interpolation of these two p values (at P ave and B tot ) using Eq. (7) is needed to calculate the final p value corresponding to P , B , tab ave tot and T . The optional Lagrangian interpolation scheme c offered by the LWRARC code is also considered an acceptable method for interpolating the decay heat data, but is not discussed in this section. 5.2.2 The Short Cooling Time Factors f 7 and fN 7 The heat rates presented in Tables 5.1–5.3 and Tables 5.5–5.7 were computed from operating histories in which a constant specific power and an uptime of 80% of the cycle time were applied. Expected variations from these assumptions cause only minor changes (
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 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: Procedure Table 5.6. PWR spent fuel
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
Page 61 and 62: Discussion Table 6.10 Computed stan
Page 63 and 64: Discussion Table 6.11 Percentage st
Page 65 and 66: Discussion Table 6.13 Summary of cr
Page 67 and 68: This section deals with inaccuracie
Page 69 and 70: Discussion Table 6.16 Summary of pe
Page 71 and 72: 7 THE LWRARC CODE The LWRARC (Light
Page 73 and 74: LWRARC Code 3. Fuel type - Select f
Page 75 and 76: LWRARC Code Table 7.2 PWR fuel asse
Page 77 and 78: 8 SUMMARY Proper methods of storing
Page 79 and 80: 9 REFERENCES 1. O. W. Hermann and R
Page 81 and 82: References 34. F. J. Sweeney and J.
Page 83 and 84: APPENDIX A DATA AND SAMPLE INPUT TO
Page 85 and 86: 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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