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120 storing the blowdown mterialb that would result froan a lnajQK Steam leak in the steam generator. Account 22, Reactor plant equipment, The reactor and associated heat-transfer system costs have been updated from the 1978 estimate using a multiplier ~f 2.5. been added for engineered safety features (which were not previoaas~y con- sidered) and for larger salt volunes, %his amount also covers external heat dissipation equipment €‘or engineered safety features. Radioactive waste handlf~g in the DMSR was estimated ta cost about the same as radioactive waste processing for the PWR. About 10% of this total (accounts 221 and 222) has Fuel handling and storage and maintenance equipment were updated from the MSBR estimate using the 2.5 multiplier. An allowance was made for the control features necessary for making the plant operate 011 the salt-steam cycle e Account 23. Turbine plant equipment. This account parallels the coal plant case, whish uses supercritical steam-cycle equipment. The feed-heating account was increased 50% to allow for tures pesultar to the Salt-%QQp applicati0R. Account 24. Electric plant equipment. Except 25 Mwe of electric heating associated with the salt similar to the PWR case. operating design fea- for provision of about loops, this account is Account 25. Miscellaneous plant equipment. The auxiliary steam sup- ply cost for the PWW has been increased to adjust the PWR cost to the DMSR basis Account 26. Main condenser heat rejection system. Design for the coal plant is comparable to the DMSW; therefore, the same costs have been assumed e Accounts 91, 92, and $3, Indirect costs. The DMSR costs are based on PWR costs adjusted upward for those accounts in which higher labor requirements are anticipated. 5,3.2 ESo~fuel oloeration and maintenance cost Estimates of nonfuel operation and maintenance (06M) costs of 2.82 wills/kh% are based on the single-unit base-load plant. me procedure ._
- ,.,.,.,., p .. ..... . G is based on the ONCOST code. IO4 121 maintenance materials, supplies and expenses, nuclear liability insur- * Annual expenses are derived for staff, ante, operating fees, and general admlnistrative activities. Operation and maintenance costs are presented fn 1938 dollars and are divided into fixed (demand related) and variable (energy-related) components. Staff requirements are given in Table 3% for a one-unit plant. An- nual costs have been derived from the O&M cost code with modifications to adjust the maintenance-labor ratio to 70:30. Estimates were that a DKSR might require major plant work at ten-year intervals (over and above PWR requirements), for which maintenance labor was increased -50%. me summary of annual 6&M costs is given in Table 34, 5.3.3 Decommissioning and disposal cost Costs for decontamination and decommissioning of the facilities would be incurred at the end of plant life. A nuellear waste working group cow- prised of DOE, Nuclear Regulatory Commission (NRC), and Environmental Pro=- tection Agency (EPA) officials is working to identify legislative needs on handling nuclear wastes, Preference is wow given for dependence on "engineered and natural barriers" for controP of on-site material after decommissioning with fall-back dependence on institutional controls for a "finite time.'o The group also opts for dismantling a decommissioned site after a short decay period, rather than either of two other sptisns, which are entombing and mothballing nuclear facilities. The cost of dismantling a DMSR is expected to be greater than for an LWR because the activity level of components in the primary circuit is higher. A number of estimates of the decommissioning cost of LWRs have been prepared; as a basis for our estimates, we have selected a representative recent (1978) estimate by the Tennessee Valley Authority (TVA) far their Yellow Creek plant early site review. The estimated de- commi~sioning cost for this plant was $78 million for a BWR. If we as- sume that the cost for a DMSW would be about 10% greater, then the estimated decommissioning cost for a DMSR would be about $86 million. A "This is excluded during construction period when no fuel is on site.
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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
Page 23 and 24:
.. . E 6> I S N 0.45 k- 0.50 B --.
Page 25 and 26:
:.:..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
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 and 122: 115
Page 123 and 124: aa 7 some components in common with
Page 125: Ae eo un t No * Table 3%. Capital c
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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