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138 probably could be developed in about 30 years; with additional support %or IID&D, the technology for on-Bine fuel processing could be developed on about the same time schedule. Although the DMSR characterizations presented in this report are ap- proximate, they provide as much detail as is justified by the very preliminary status of the system conceptual design. -Any effort to substan- tially improve the quality and detail of the characterizations would have to be accompanied by a significant system design effort oriented toward a specific DMSW power plant. Costs and times required for such studies would be several times as large as those for the preliminary work and probably could be justified only if a national decision were made to re- establish a federally funded MSR program. Any MSR program of substantial size presumably would include an RD&D effort of some size to support effective pursuit of program goals. This work, in turn, would be complemented by the design studies which would help to define RD&D tasks and focus the entire effort. The combination would allow the attainment of objectives on the shortest practical time schedule 8 From the preliminary studies reported, a once-through DMSR without on-line fuel processing apparently would be the most reasonable choice for development if an RD6D program were established, Nowever, parallel development of the technology for ~ontin~ous fuel processing would add only moderately to the total progrm cost and could provide the option of a more resource-efficient (and possibly a cheaper) fuel cycle. c ... ..... .:. -7
139 The authors want to acknowledge the extensive and able support of the Union Carbide Corporation Computer Sciences Division, especially J e R e Knight, Ne M e Greene, 0. W e H~P~BPPIP, W e M e Westfall, W e E. Ford 111% B. R. Biggs, and E. Me Petrie. The nuclear calculations depended heavily on their advice and help. The estimate of capital, operating, and decomissianing costs for the DMSR were prepared and reported by PI. L. Myers.
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i *w . . I
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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
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...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
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would be expected to have an equili
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.... . . . . :i ,.*,&s 57 Corrosion
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. ;;..,..I . . . . . . "LW 0 9 m -
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of the fissioned atom. ea ~arly ass
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63 n e results of a program of solu
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65 Table 27. Sources and rates Sf p
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operation of the PISRE. 67 analyses
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UP3/UF4 ratio would be possible. DM
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$ .p9 3.3.3.1 Preparation of initia
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73 Contamination of fuel by seconda
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*w- through the walls of the primar
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77 4 will apparently be necessary (
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such contamination. For a demonstra
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8% 3.4 Reactor Materials Although s
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: ....., . .’ -. ..WY used in the
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..... 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 112: and the ~ dvent (or carrier) salt a
Page 113 and 114: BO 7 TPle fuel makeup requirements
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: 137 includlng $900 million for the
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: .... ..
Page 162: 156 77. He 6. MacPherson, Institute
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