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

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59. 60 * 61 e 62 e 63 B 64 0 65. 66. 67. 68. 144 E. M. Toth arnd %. 0. Gflpatriek, "Equilibria of UP~R~UI~I Carbides in Ksbten Solutions of UF3 and UF4 Comtained in Graphite at 850°K," 6. bizorg. TJtkeZ. &em. 35, 1509 (197%). We a. G~ime~, "MaterFaEs Problems in Molten-Salt Reactors," in Mateeals and &eZs for High Temperature K7ticlear hhergy Appl.ieatG.ms, ed. by Me' T. Siranad and L. R. Zramwlt, The MHT Press, Mass., 1964. W. W. Grimes et al., "Chemical Aspects of Molten Fluoride-Salt Reactor Fuels," in Fluid FueE Rea@to~s, ed, by J. A. Lane, H. 6. XacPkerssn, and F, Flmslan, Addison-Wesley, Reading, Pa., 1958. .VoZten-Salt Reae-top Program Progress Report fop Peptiod f~om March I -to August 31, 2961, ORNk-3215, pe 117. W. R. Grimes, Radiation Chemis-tvy of Molten-SaZt Reactor System, OWNLITPI-500 (March 31, 1963) e Reactor Chemistry Division Annmt BP.ogress Report fop Pe~iad Ending c7anuary 31, 1962, ORNL-3262, p* 20.
...... &;.& 3 14 5 74. W, R. Grimes, Ne V. Smith, and 6. PI. Watson, "Solubility of Noble Gases in Molten F1u~ride~; I. In Mixtures of NaF-ZrP4 X> and N~F-zPP~-uP~ (560-46-4 mole Z>," 6. $hysB &em. (1958). (53-47 mole 62, 862 75. Me Blander et al., "Solubility sf Nsble Gases in Molten PIuorides; 61. In the LIF-NaF-KP Eutectic Mixtures," Je Phys. &em. 63, E164 (19591 0 77. W. B, Briggs and R. Be Korsmeyer, MoZten-Sali5 Reactor P m g m Semi- annual fiogress Report for Period €%ding February 28, 2970, CXNL- 4548, pe 53. 81. D. L. Manning and G. Mammilntov, Moltm-Salt Raactor fiogrm Semi- aplnuaz Progress R6qmr-b for Period ming February 29, 1976, ORrn- 5132, p* 38, 83. W. R. Grimes et al., "High Temperature Processing of Molten Fluoride Nuclear Reactor Fuels,'* Nttct. &g. Part VII 55, 27 (1959). 84. G. J. Nessle and W. R. Grimes, "Production and Handling of Molten ~luorides for Use as Reactor Fuels," fiemieal Engineering Pksgress Symposiwn Series 56(28) (19601. 85. J. H. Shaffer, Preparation and Hadling of Salt Mixtures for the Molten-Salt Reaet& Experiment ORNE-4616 (January 1971 le 86. R. B. Eindauer, Molten-Salt Reactor P~ogram SemiannuaZ Report for P%PiOd Ending August 31, 1971, ORNL-4728, pa 226. 87. W. B. Llndauer, Moltan-Salt Reactor P~ogm Semiannuat Repore for Period Ending Feb~uary 28, 9971 ORNL-4676, p. 269.
Page 1:
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 --.
Page 25 and 26:
:.:..y ,. . . w, E9 The code calcul
Page 27 and 28:
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
Page 43 and 44:
where Ci = relative delayed-neutron
Page 45 and 46:
.... . . . . , 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
Page 57 and 58:
.. .*,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
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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 and 148: . ... . .,.,.,.,.,. . , i.rc- q....
Page 149: .:. _.i .. ..... -.=* 45. A. L. Mat
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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