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

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122 Table 33. Staff requirement for one 1-GWe DNSR power plant Employee type Number Plant manager's office Manager Assistant Quality assurance Environmental contr~l Public relations Training Safety Ad~ainistration and services Health services Security Operatisms Sub t 0 tal Subtotal Maintenance Supervision Crafts Peak maintenance, annualized Subtotal Technical and engineering Reactor Radiochemical Instrumentation and control Technical support staff Subtotal Total Less security Less security and peak mintemance 1 i 3 1 1 1 1 13 1 66 89 2 33 35 8 16 96 - 120 1 2 2 17 - 22 - 2 66 280 184 L; ..." . v.< . . . . . . ... . . -3
123 Table 34. Summary of annual nonfuel Q&M costs for base-load steam-electric power plants in 1978. oa Plant type Number of units per station Thermal input: per unit, 'MWt Plant net heat rate Plant net efficiency, 2 Power output, net, me Annual net generation, million lewh Pl ant f ac to P Annual costs, thousands 0% dollars Staff, 266 persons at $23,412 Maintenance material Fixed Variable Supplies and expenses Fixed, plant Variable, plant Insurance and fees Comercial liability bnsuranee Government liability insurance Retrospective premium Pnspe~tio~~ fees and expenses Administrative and general Total fixed costs Total variable costs Total annual OdM costs Unit costs, mills/k%(e) Fixed unit O&M costs Variable unit O&M costs Total unit O&M costs DMSR with evaporative cooling towers P 2270 7755 44 0 00 PO00 6570 8.75 6228 6555 6555 6 3317 3800 317 488 2 84 18 6 100 2367 18,500 31 7 18,875 2*75 0.07 2.82 aExcludes <strong>the</strong> salt inventory losses; assumes nuclear insurance at LWR sates.
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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
Page 23 and 24:
.. . 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
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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
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 and 126: Ae eo un t No * Table 3%. Capital c
Page 127: - ,.,.,.,., p .. ..... . G is based
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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