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

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31 e 32 8 33 0 34 35 a 36 m 37. 38 0 39 D 48. 41 8 42 0 43 e 142 6. J. Barton et al., Solubility 0% Cerium Triflusside in Molten Mfxtures 0% Lithium, Beryllium, and ~%oriurn ~Euorides," Inorg. Cic.ern. $e 309 (1970). C. F. Baes, Jre9 p. 617 in "'Sywposim on Wepr~ces~ing of Nuelear Fuels," ed. by P. Chiotti, vol. 15 of A%&?tGaP Metaz~urgy, USAEC-CQNF 690801, 617 (%969)e 8. G. ROSS, C. E. Bamberger, and e. F. Baes, 9%. , "The Oxide Cpeemis- try sf Protactinium in ~olten Fluorides," J. hop+ JIucZ. &ern. 35, 433-49 (1973). C. E, Bamberger, R. 6. Ross, and C. F. Baes, Jkc, M~Ztapz-Satt Rea@tor P F Q ~ Semiannual P ~ PPQ~WSS Report for Pe~i~d Ending February 29, 9972, ORWE-4782, p. 72.
.:. _.i .. ..... -.=* 45. A. L. Mathews and 6. P. Baes, Jr., "Oxide Chemistry and Thems- dpad.cs of Molten EiF-BeP2 SoPution," Insrg. &ern. T9 373 (1968). 47. #. E. McCoy et al., "New Developments In Matesiah for Molten-Salt Reactors," #Uet. Appt. ?%dwlot. 8, 156 (February 1970). 48. 8. E. McCoy, "Materials for Salt-Containing Vessels and Piping9" chap. 7, p. 195 in fie Deve~opmePzt Statu8 of Molten-Salt Breeders, QRNL-4812 (August 1972). 51. W. B. Csttrell et al., Bisassembty and Postoperative Ezmimtion of the Aircraf% Reaetor Ezperirnmt, ORNL-1868 (April 2, 1958), 52. W. D. Manly et al., Aircraft Rmctor Experiment -MetalZurgica% As- pets, ORNL-2349, pp. 2-24 (December 20, 1957). 53. We D. Manly et a%., "Meta%lurgicah Problems in Molten Fluoride Systems," in F?agr. Nuel. dEnergy S~F. IV !?'eehnol~gy, figineering ad safety 2, 164 (1960). 54. W. D, Manly et al., ptuid he1 Reae-tors, pp. 595-604, ed. by James A. Lane, H. G. MaeHkerssn, and Frank Maslan, Addison-Wesley, Read- ing, Pa. (1958). 55. Molten-Salt Reactor pvlogm Status Repor.f;, ORNL-CF-58-5-3, pp. 112-13 (May 1, 1958). 56. J. N. DeVan and R, B. Evans, 111, pp. 557-79 in Confmence on Co+ rposion of Reactor Ma-ter-Lal.8, June 4-8, 9962, Proceedings, VoZ. I1 International Atomic Energy Agency, Vienna, Austria, 1962. 57. F. F. Blanken9kip,MoZten-SaZt Reactor Program Sern&znntcai? Prop rem Report for Period Ending July 31, 1964, QRn-3708, p. 252. 58. S. S. Kirslis and P. F. Blan~enship,Mottan-~aZt Reactor &.ogrcun Sem-LannuaZ Progress Report. for Period katling August 31, 196Bs ORm-4344, p. 115.
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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
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 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: . ... . .,.,.,.,.,. . , i.rc- q....
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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