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116 The construction cost of the MSTR way be estimated by updating the cost estimate for the MSTR prepared in 1395 for the MSBR program. Using a construction materials and labor increase of P2%/year gives a multiplier of 1.4 and a cost for the MSTR in 1978 of about $680 million. A detailed estimate of the cost of a l0QO-MWe DMSR based on a mature technology is given in it fol%owing seetion, From this, we have estimated the cost of a first standardized DMSR by applying a factor of 1.5 to allow for increased first-of-a-kind costs and the cost of a lead CQIIIIIW~C~~ prototype by applying another factor of 1.5 to allow for increased prototype costs, Using this proceduree the cost of a POOO-Mk prototype DMSR is estimated to be $1470 miPliom and the first standardized DMSR $980 million The prototype DMSR need not be as large as 1800 MWe; the cost could be reduced some, for example, by building a 5OO-We prototype with two steam-generator Poops rather than four. Estimating the probable cost of experimental and prototype reactors fn advance of design is exseedingPy difficult. The cost estfmates presented were made by a staff that has had experience in the design and operation of experimental reactors, particularly the MSRE. glke MSRE was constructed and operated within budget, which is an indication that the technology is reasonably well understood and that cost estimates for fu- ture reactors are probably realistic, if R Q ~ absolutely accurate. Con- verselye the proposed reactors are a large step up in scale from the MSRE and would be subject to the vagaries of the licensing process for a new reactor type, These factors introduce uncertainties into the cost estimates whish are beyond evaluation at the present time. 5.3 Economic Performance of Commercial DMSR The projected cost of power from a c~m~r~ial DMSR can be estimated only approxhately because the DMSR is in the conceptual stage and not even a detailed conceptual desfgn has been prepared. However, by taking advantage of the similarity of the BMSR to the MSBR (for which a detafled conceptual design and cost estimate have been prepared) and by carefully comparing the DMSR with EWW and coal-fired power plants (which would have . .. . . . .... . . w.:. .>
aa 7 some components in common with or similar to those of a DMSR), a reason- able cost estimate can be made. A cost estimate was prepared for the MSBR in 1998 and appears in Ref. 8. These costs were taken (for most accounts) as the basis for the DMSR estimate using the following method. 1. TIE costs were adjugtea to take into account the differences PH~ size or other requirements for the DMSR. For example, the reactor vessel cost was increased to take into account the larger size of the BMSR vessel0 2. The 1978 costs were increased by a multiplier based on the increase in construction materials and labor costs from 1978 to 1978. 'Fhe multiplier was calculated to be in the range 2.3 to 2.5; to be c~nse%~a- tive, the multiplier 2.5 was used. This represents an annual rate of increase of about 12X, In addition, the costs of a pressurized-water reactor (PWR), a bailing-water reactor (BUR), and a coal-fired plant in 1978 were estimated usimg the CONCEPT V code. "3 accounts were estimated based the analogous account in one of the CONCEPT estimates. For example, the turbine-generator cost was based on the coal-fired plant estimate because the same type of supercritical steam turbine would be used. mere appropriate, some DMSR cost En reporting the results, the cost estimates for the PWK and (in the appendix) the coal-fired plant are given for comparison. of the BWR were not substantially different from the PWR.) (The costs The results of the estimates for capital, monfuel operation and maintenance, and decommissioning costs are presented in the next three sections. The fuel cycle costs were calculated independently and are presented in a fourth section. 5.5.1 Capital costs The bases for the capital cost estimates are given in Table 31. Some minor adjustments in the code of accounts used in the 1970 MSBR cost estimate were required to c~nfom-m to the present code of accounts.
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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
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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
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 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: 115
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: .... ..
Page 162: 156 77. He 6. MacPherson, Institute
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