ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site

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156 77. He 6. MacPherson, Institute for Energy Analysis, Oak Ridge Associated Unfversitfes, Oak Ridge, TN 37838 78. I%. Omberg, Wanford Engineering Development Laboratory, P.0. Box 79. 1970, Richland, WA 99352 E. Straker, Science Applications, 8400 Westpark Drive, McLean, VA 22601 80. A. Me Weinberg, Institute for Energy Analysis, Oak Ridge Asssciated Universities, Oak Ridge, TM 37830 81-181. For distribution as shorn in DOE/TEC-4500 Molten-Salt Reactor Technology under category UC-76, . . .. .. ~ ........... . y.s2
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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
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... w . . .y and to salt containing
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With the different ~Bjectives of ns
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t.;$- ... quite different from thos
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93 during noma1 operation. Minor am
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............. . . .. . .=w as SSm,
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. . . :.w . . . . , 4. ALTERNATIVE
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.. . ... . . . . . . .. . . "W 3. T
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.,.. w .." by removing some uranium
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, . . . . . . , -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 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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