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124 large uncertainty is present in this estimate, of course, because of the limited experience in decommissioning. However, the cost sf decommissioning does not appear to be a large fraction of the cost of the construc- tion, and the present worth of expenditures to be made in the future is small. 'Fhe present worth of the estimated cost of decommissioning a DMSR 40 years after start-up, discounted to the start-up date at a 4.5% dis- count factor, would be about $15 million. 5.3*4 Fuel cvcle costs A% this stage of development and optimization of a ~n~e-through DMSR, several assumptions are necessary if a fuel cycle cost is to be estimated. One assumption 1s that the initial fuel charge will consist of 74 mole 2 7LiF, 16.5 mole % BeF2, 8.23 mole 2 ThF4, and 1.27 mole X UF, plus UP3. If, as seems reasonable, an afkswanee is made for an additional 2% of molten fuel in the drain tank, the initial fuel solvent will require 149 metric tons of ThF,, E13 metric tons of LiF, and 45.6 metric tons of BO2" quired; this is equivalent to 804 metric tons of U308 and would require 8.05 x 105 swu for its enrichment. actor storage tank would consist of 33.1 metric tons (7.30 x ~ b 05 ) material In addition, 23.5 metric tons of UP, enriched to 20% in 23% is re- Tke purified fuel delivered to the re- Total cost of the initial fuel is based on U308 at $35/lb, separative work at $SO/SWU, BeF2 at $15/lb, thorium at $15/kb Tho2$ and SLiF available at $3Jg of contained ki, * AII additional $2/lb of tetrafluoride has been allotted for conversion of Tho2 to n F4 and for CQrWerSiQn of UPg to UF$. The fuel, wade by mixing the powdered ingredients, must be purified in the molten state before use (as described in previous sections), Given the component fluorides at the prices above, the assunaption is that this purification can be performed for $$/lb of finished product. With these assumptions, the total cost of the initial DMSR fuel charge is near $225 million (see Table 35). If we assme that the annual * his is the official price for small quantities of ~9,99+ a ~ i for use in PWRS. It is almost certainly too high (probably five-fold) if lithium were actually used in such quantities.
...... . . . . ., x.:w* 4 i.. ... __ . . . . 125 Table 35. Cost of initial fuel charge for once-through DMSR (331 metric tons fuel) Fuel solvent Mater tal s Fuel 'LiF (30.46 metric tons lithium at $3/g) ThP4 (127.68 metric tons Tho2 at $€5/Pb) BeP2 (45.60 metric tons at $15/lb) Uranium (883.8 metric tons U308 at $35/lb) Separative work (8.05 x 105 swu at $80) Conversion and purification msrium (148.96 metric tons ThP4 at $2/lb) uranium (23.50 metric tons U F ~ at $2/%b) Fuel mixture (331.2 metric tons at $6/lb) Total cost of initial fuel Annual charge (12%) cost (dollars) use charge is 122, this initial fuel contributes $26.9 mfllion/year to the fuel cycle cost. A once-through DMSR must add uranium at more os less regular inter- vals over its operating lifetime. Though other modes of addition are possible, for this assessment we assumed that the uranium additions will be made as a liquid 'LiF-UFk mixture containing 30 mole % UF4 (melting at about 540OC) e Such additions would appreciably increase the 'LFF con- centration of the fuel. Adjustment of the UP3/UF4 ratio is assumed to be done by in situ reduction of UF4 with metallic beryllium. The fuel stream is assumed to be treated (once in each 1008 full-power days) with an an- hydrous HF-Hz mixture to remove inadvertent oxide contamination; the re- sulting oxidation of UF3 is managed by additional. reduction with beryllim. With this mode of operation, BeF2 equivalent ts nearly 6% of that in the original fuel charge would be added over the reactor lifetime. Such additions of ?LiF and BeF2 dilute the fuel and appreciably increase its volume so that an increasing (though relatively small) fraction of the
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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
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 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: 123 Table 34. Summary of annual non
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: .... ..
Page 162: 156 77. He 6. MacPherson, Institute
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