nureg/cr-6700 - Oak Ridge National Laboratory

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Radiation Shielding Section 5 0.16 Neutron Dose Fraction 0.14 0.12 0.1 0.08 0.06 2 years 5 years 20 years 100 years 0.04 0.02 0 0 20 40 60 80 Burnup (GWd/t) Figure 13 Relative contribution of neutrons to the total dose rate for 5-wt % PWR fuel, con<strong>cr</strong>ete storage cask 34
Section 5 Radiation Shielding 0.6 0.5 2 years 5 years 20 years 100 years Neutron Dose Fraction 0.4 0.3 0.2 0.1 0 0 20 40 60 80 Burnup (GWd/t) Figure 14 Relative contribution of neutrons to the total dose rate for 5-wt % PWR fuel, steel transport cask 35
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 10 and 11: LIST OF FIGURES (continued) Figure
Page 12 and 13: LIST OF TABLES (continued) Table Pa
Page 14 and 15: xii
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 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
Page 64 and 65: Radiation Shielding Section 5 Table
Page 66 and 67: Radiation Shielding Section 5 Table
Page 68 and 69: Summary Section 6 Table 13 Summary
Page 70 and 71: Summary Section 6 56
Page 72 and 73: Conclusions and Recommendations Sec
Page 74 and 75: References Section 8 13. S. M. Bowm
Page 77 and 78: APPENDIX A COMPUTER CODE INPUT AND
Page 79 and 80: Appendix A Computer Code Input and
Page 99 and 100:
NUREG/CR-6700 ORNL/TM-2000/284 INTE
Page 101:
90. H. Okuno, Japan Atomic Energy R
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