nureg/cr-6700 - Oak Ridge National Laboratory

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LIST OF FIGURES (continued) Figure Page 18 Neutron source from 1 metric tonne (t) of PWR fuel; 27.5 GWd/t ....................................................... 39 19 Neutron source from 1 metric tonne (t) of PWR fuel; 60 GWd/t .......................................................... 40 20 Relative importance of the dominant spontaneous fission actinides for 5-wt % PWR fuel, 5-year cooling ........................................................................................................................................ 42 21 Relative importance of the dominant spontaneous fission actinides for 5-wt % PWR fuel, 100-year cooling .................................................................................................................................... 43 22 Fraction of total dose from dominant nuclides in 5-wt % PWR fuel; steel transport cask, 5-year cooling ........................................................................................................................................ 44 23 Fraction of total dose from dominant nuclides in 5-wt % PWR fuel; steel transport cask, 100-year cooling .................................................................................................................................... 45 24 Fraction of total dose from dominant nuclides in 5-wt % PWR fuel; concrete storage cask, 5-year cooling ........................................................................................................................................ 46 25 Fraction of total dose from dominant nuclides in 5-wt % PWR fuel; concrete storage cask, 100-year cooling .................................................................................................................................... 47 26 Fraction of total dose from dominant nuclides in 5-wt % PWR fuel; lead cask, 5-year cooling ........................................................................................................................................ 48 27 Fraction of total dose from dominant nuclides in 5-wt % PWR fuel; lead cask, 100-year cooling .................................................................................................................................... 49 viii
LIST OF TABLES Table Page 1 Burnup and enrichment ranges used in high-burnup ranking studies.......................................................5 2 Fuel assembly specifications ....................................................................................................................6 3 Assembly structural material masses........................................................................................................7 4 Criticality-safety rankings for dominant actinides in PWR fuel ............................................................16 5 Criticality-safety rankings for dominant fission products in PWR fuel .................................................17 6 Criticality-safety rankings for dominant actinides in BWR fuel............................................................19 7 Criticality-safety rankings for dominant fission products in BWR fuel.................................................20 8 Radionuclides decay-heat rankings for PWR fuel..................................................................................29 9 Radionuclides decay heat rankings for BWR fuel..................................................................................30 10 Most important nuclides in cask shielding calculations .........................................................................41 11 Shielding rankings for dominant radionuclides in PWR fuel.................................................................50 12 Shielding rankings for dominant radionuclides in BWR fuel ................................................................52 13 Summary of actinide rankings by analysis area (20-year cooling time).................................................54 14 Summary of fission- and activation-product rankings by analysis area (20-year cooling time) ............55 A.1 Example of SAS2 input listing used to generate PWR isotopic compositions.......................................63 A.2 Example of SAS2 input listing used to generate BWR isotopic compositions ......................................66 A.3 ORIGEN-S and SAS1 shielding analysis input files (steel cask model)................................................69 A.4 Example of input listing for total dose for steel cask .............................................................................71 A.5 Example of input listing for total dose for concrete cask .......................................................................73 A.6 Example of input listing for total dose for lead cask..............................................................................75 A.7 Example of OPUS input file for absorption rankings.............................................................................77 A.8 Example of OPUS nuclide importance listing output for absorption rankings ......................................78 ix
Page 1 and 2: NUREG/CR-6700 ORNL/TM-2000/284 Nucl
Page 3: NUREG/CR-6700 ORNL/TM-2000/284 Nucl
Page 7: CONTENTS ABSTRACT..................
Page 12 and 13: LIST OF TABLES (continued) Table Pa
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Page 16 and 17: Introduction Section 1 Finally, sev
Page 18 and 19: Analysis Approach Section 2 70000 6
Page 20 and 21: Analysis Approach Section 2 Table 2
Page 22 and 23: Analysis Approach Section 2 using t
Page 24 and 25: Criticality Safety Section 3 1 Abso
Page 26 and 27: Criticality Safety Section 3 Absorp
Page 28 and 29: Criticality Safety Section 3 Absorp
Page 30 and 31: Criticality Safety Section 3 Table
Page 36 and 37: Criticality Safety Section 3 The fi
Page 38 and 39: Decay Heat Section 4 10000 Decay He
Page 40 and 41: Decay Heat Section 4 4.1 Decay-Heat
Page 42 and 43: Decay Heat Section 4 1 Fraction of
Page 44 and 45: Decay Heat Section 4 Table 9 Radion
Page 46 and 47: Radiation Shielding Section 5 0.025
Page 48 and 49: Radiation Shielding Section 5 0.16
Page 50 and 51: Radiation Shielding Section 5 1 0.9
Page 52 and 53: Radiation Shielding Section 5 Neutr
Page 54 and 55: Radiation Shielding Section 5 Figur
Page 56 and 57: Radiation Shielding Section 5 1 Rel
Page 58 and 59: Radiation Shielding Section 5 Fract
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Radiation Shielding Section 5 Fract
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Radiation Shielding Section 5 Fract
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Radiation Shielding Section 5 Table
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Radiation Shielding Section 5 Table
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Summary Section 6 Table 13 Summary
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Summary Section 6 56
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Conclusions and Recommendations Sec
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References Section 8 13. S. M. Bowm
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APPENDIX A COMPUTER CODE INPUT AND
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Appendix A Computer Code Input and
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NUREG/CR-6700 ORNL/TM-2000/284 INTE
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90. H. Okuno, Japan Atomic Energy R
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