nureg/cr-6700 - Oak Ridge National Laboratory

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Computer Code Input and Output Listings Appendix A 5 114.0 4 0 end zone ndetec=1 read xsdose ' 2 det. @ 1" ans 2' from surface(114.0) 365.76 116.54 182.88 end last tn24p with 24 unconsolided fuel assemblies cylinder ' source position 5/6/8/12 =(3/5/20/100 years) 1 72.25 60 +1 0 0.0 71 12 5.998+6 11.04 2 72.75 2 0 3 99.75 40 0 4 113.0 25 0 5 114.0 4 0 end zone ndetec=1 read xsdose ' 2 det. @ 1" ans 2' from surface(114.0) 365.76 116.54 182.88 end 72
Appendix A Computer Code Input and Output Listings Listing A.5 Example of input listing for total dose for con<strong>cr</strong>ete cask ' $HOME/nrc/ranking/pwr/tot_vsc_pwr_4e_60g.in ' ' this case begins with the concentrations in position 5 of ft71f001 ' which has 12 positions. position 1 has the end of irradiation ' concentrations from the sas2 case. position 2 has the concentrations ' from the end of the sas2 decay case (zero length). positions ' 3 through 12 are from the origen-s case run separately. ' =shell cp $RTNDIR/pwr4e_60g.ft71f001 ft71f001 end =sas1 parm='size=300000' 1-d radial model of vsc with consolidated fuel smeared over 63. cm 27n-18couple infhommedium ' mixture 1, homogenized fuel zone: fuel pins, clad, & basket uo2 1 .377 293 92235 3.0 92238 97.0 end zircalloy 1 0.109 end ss304 1 .102 end ss304 2 end ' mixture 3, ordinary con<strong>cr</strong>ete h 3 0. 7.77-3 end o 3 0. 4.39-2 end na 3 0. 1.05-3 end mg 3 0. 1.49-4 end al 3 0. 2.39-3 end si 3 0. 1.58-2 end s 3 0. 5.64-5 end k 3 0. 6.93-4 end ca 3 0. 2.92-3 end fe 3 0. 3.13-4 end end comp end vsc with consolidated fuel cylinder ' source position 5/6/8/12 =(3/5/20/100 years) 1 63.0 60 +1 0 0.0 71 5 4.56+6 15.64 0 66.04 2 0 2 67.31 3 0 0 74.93 5 0 2 83.19 20 0 3 133.35 40 0 end zone ndetec=1 read xsdose ' 2 det. @ 1" ans 2' from surface(133.35) 365.76 135.89 182.88 end vsc with consolidated fuel cylinder ' source position 5/6/8/12 =(3/5/20/100 years) 1 63.0 60 +1 0 0.0 71 6 4.56+6 15.64 0 66.04 2 0 2 67.31 3 0 0 74.93 5 0 2 83.19 20 0 3 133.35 40 0 end zone ndetec=1 read xsdose ' 2 det. @ 1" ans 2' from surface(133.35) 365.76 135.89 182.88 end vsc with consolidated fuel cylinder 73
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NUREG/CR-6700 ORNL/TM-2000/284 Nucl
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NUREG/CR-6700 ORNL/TM-2000/284 Nucl
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CONTENTS ABSTRACT..................
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LIST OF FIGURES (continued) Figure
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LIST OF TABLES (continued) Table Pa
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xii
Page 16 and 17:
Introduction Section 1 Finally, sev
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Analysis Approach Section 2 70000 6
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Analysis Approach Section 2 Table 2
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Analysis Approach Section 2 using t
Page 24 and 25:
Criticality Safety Section 3 1 Abso
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Criticality Safety Section 3 Absorp
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Criticality Safety Section 3 Absorp
Page 30 and 31:
Criticality Safety Section 3 Table
Page 32 and 33:
Page 34 and 35:
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
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 85: 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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