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106 Table 29, Performance data for long-term fuel cycle options for DMSRS" with full-scale f ission-product removal Conversion ratio after 20 years 300 years 608 years Requirement for initial core asaaing U398S rn Separative work, Mg SWU Average requirement %or fuel makeup per 30-year cycle k$$, @3 During years 0--300 During years 301-600 Separative work, Mg SW During years 0-380 During years 301-600 Uranium reenrichment, m/year Uranium discara, ~giyear Fissile i ~~entory at equiPlbrium, Ng ur aR ium All fissile nuclides Option b A B c D 0.90 0.74 6 0.94 0.92 0.92 0.94 0.93 0*93 0.94 0.89 0.89 860 860 860 988 860 890 860 980 1000 c 1000 e 0 0 d 1.2 a 3.2 428 460 440 478 0 0 2.9 3.1 %or 1 G W ~ at 75% capacity factor. b~ee text for characterization of options. Mot operable beyond 300 years. dAt 300 years. The tabulated results show that all four of these options would maintain relatively high conversion ratios for very long times. The U308 resource 5 80 600 580 60 0 0 0.24 2.7 3.0 500 600 requirements for the initial core loadings are all similar, and all are slightly higher than that for the once-through fuel cycle (because sf the volume of fuel in the processing system). 50 8 60 0 0.60 0 2e8 3.1
BO 7 TPle fuel makeup requirements are expressed in metric tons of UaOg for 30 years of operation in a 1-GWe plant at 75% capacity factor and are averages for ten 30-year cycles. The effect of this averaghg is most pronounced for option A; the fuel makeup requirement is only a fraction of the average for the first one or two reactor lifetimes and is somewhat greater than the average for the last cycles. Thus, while this option would require more uramim than the others in the very long tern, its per- fomance for the first few reactor lifetimes would be quite attractive. Even for the long-term, this resource requirement would be well below that of current-generation LWRs. Option B illustrates the long-term sav- ing in uranium resources that could be achieved if higher enrichments could be tolerated for the relatively small amsunts of makeup fuel, Be- cause the resource savings are principally long tlem and the required uranium enrichment exceeds currently perceived denaturing limits this appears to be OR^ of the less gromhsi~~g options, The two remaining 0p- tions, C and D, both show favorable resource utilization properties for long times with only minor penalties for discarded uranium (option C> or uranium subjected to reenrichment (optism B), Of these, option P) clearly would be preferable if reenrichent were an acceptable procedure Tke preceding four converter options and/or the break-even breeder would require the availability of a cornpPex and expensive fuel cleanup facility withh the primary containment of each reactor installation. The technology for an integrated proeessfng facility has not been fully developed, and past work clearly indicates that a substantial development effort would be required to produce a commercially functional system. Even then, the capital, operating, and maintenance costs of such a system possibly would have a signiffcant adverse impact on the overall economic perforname of the associated DMSR. Other factors to be considered for these options included the willingness of the reactor operator to assme * Conceivably, a single cleanup facility could serve several reactors at a cornon site, but such an arrangement would complieate the 0peratiQn and would add problem~ of inventory accountability among the various units. Jk
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P iii CONTENTS ....................
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CONCEPTUAL DESIGN CHARACTERISTICS O
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3 The primary purpose of this study
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.. .... . w..w c Y ... . r 5 2. GEN
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ii.... :.: ..... .,. \ ..... %& . 3
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addition StathQR would be required.
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!I \.... . , . ~ .... .. . . / I I
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... .. ...... . . . $i 13 Table 1.
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15 Initial scoping studies showed t
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.. . E 6> I S N 0.45 k- 0.50 B --.
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:.:..y ,. . . w, E9 The code calcul
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h 3. Additional 238Y is added as re
Page 29 and 30:
...z,y .. . c .A, Table 9. Actinide
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';x.w' .... Relative power distribu
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........ . . . :..i 27 a Inner 2.54
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29 Table 16. Effect of neutron spec
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ob E 2 a 4 5 6 7 8 9 10 11 12 13 14
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.. . . . . . . . . . 'a# 0.1 0.2 0.
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35 (Doppler effect), (2) changing t
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where Ci = relative delayed-neutron
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.... . . . . , c.y..p c "
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.... :...w . . . . . :, %. , dimens
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,. ::.y ~. . .... , 40 0 43 1 2 3 4
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.,.,. . . ., , .. . . . . . . . %..
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.... ... . ....... . .%.W 3.3.1.1 C
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49 Variation of fuel composition wi
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.. .*,p. . . . . . . . Table 25. Ph
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;: c.... x. . w ..i 53 Table 26, St
Page 61 and 62: would be expected to have an equili
Page 63 and 64: .... . . . . :i ,.*,&s 57 Corrosion
Page 65 and 66: . ;;..,..I . . . . . . "LW 0 9 m -
Page 67 and 68: of the fissioned atom. ea ~arly ass
Page 69 and 70: 63 n e results of a program of solu
Page 71 and 72: 65 Table 27. Sources and rates Sf p
Page 73 and 74: operation of the PISRE. 67 analyses
Page 75 and 76: UP3/UF4 ratio would be possible. DM
Page 77 and 78: $ .p9 3.3.3.1 Preparation of initia
Page 79 and 80: 73 Contamination of fuel by seconda
Page 81 and 82: *w- through the walls of the primar
Page 83 and 84: 77 4 will apparently be necessary (
Page 85 and 86: such contamination. For a demonstra
Page 87 and 88: 8% 3.4 Reactor Materials Although s
Page 89 and 90: : ....., . .’ -. ..WY used in the
Page 91 and 92: ..... i.. ....., . .Yd 85 QRPIL-DWG
Page 93 and 94: ... w . . .y and to salt containing
Page 95 and 96: With the different ~Bjectives of ns
Page 97 and 98: t.;$- ... quite different from thos
Page 99 and 100: 93 during noma1 operation. Minor am
Page 101 and 102: ............. . . .. . .=w as SSm,
Page 103 and 104: . . . :.w . . . . , 4. ALTERNATIVE
Page 105 and 106: .. . ... . . . . . . .. . . "W 3. T
Page 107 and 108: .,.. w .." by removing some uranium
Page 109 and 110: , . . . . . . , -c%w probably still
Page 111: and the ~ dvent (or carrier) salt a
Page 115 and 116: 5. CQPIPIERCIWLPZATION CONSIDERATIO
Page 117 and 118: 11% At the close of MSRE operation,
Page 119 and 120: 12YS 75 22”” 955 30” 1””
Page 121 and 122: 115
Page 123 and 124: aa 7 some components in common with
Page 125 and 126: Ae eo un t No * Table 3%. Capital c
Page 127 and 128: - ,.,.,.,., p .. ..... . G is based
Page 129 and 130: 123 Table 34. Summary of annual non
Page 131 and 132: ...... . . . . ., x.:w* 4 i.. ... _
Page 133 and 134: E2 7 There are no detailed estimate
Page 135 and 136: 129 particularly if such activities
Page 137 and 138: . ~.........* . . . . . :*. ... . -
Page 139 and 140: . .. . . . . . . . ;.:w b 133 the i
Page 141 and 142: _... ..&/ ; .; with reactor scram m
Page 143 and 144: 137 includlng $900 million for the
Page 145 and 146: 139 The authors want to acknowledge
Page 147 and 148: . ... . .,.,.,.,.,. . , i.rc- q....
Page 149 and 150: .:. _.i .. ..... -.=* 45. A. L. Mat
Page 151 and 152: ...... &;.& 3 14 5 74. W, R. Grimes
Page 153 and 154: p 103. 6. Re Hudson 11, CQNCEPT-5 U
Page 155: ... . . . . . . . , . ,.Y&fl 149 ap
Page 158 and 159: Account No. -0- Three- digit digit
Page 160 and 161: .... ..
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156 77. He 6. MacPherson, Institute
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