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

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1. 2. a. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. REFERENCES Le E. MeNeese and M. W. Bosenthal, "MSBR: A Review of the Status and Fut~re,'~ flucZ, flews 1%(12), 52-58 (September 19741. Re We Roberts, Energy Research and Development Administration, let- ter to H. PQS~IM, Oak Ridge National Laboratory, March 1, 1976. FI. F. Barnan et ale, Molten-Salt Reactor Conceg-bs hth Redwed Potential fop? fio~iferation of Special NucZear MateP-.Zals, Institute for Energy Analysis, OWAU/IEA(M) 77-13 (February 1977). Gerald R. Ford, "Statement by the President on Nuclear Policy,'" Bf- fice of the White House Press Secretary, October 28, 1976. Department of Energy, Nonprolifepat&m AZterrea-biue Systems Assemfiogrm plan, Assistant Secretary for Energy Technology Nuclear Energy Pk~gra~~~s, Office of Fuel Cycle Evaluation (April 1978). Jimmy Carter, "Statement on Nuclear Power Fdicy9'* press release dated April 7, 1977, Bept, state BUZZ. 76, 429-33 (May 2, 1977). Executive Office of the President, ate National. P~SP~LJ Plan, April 29, 1977, G. T. Mays, A. Ne Smith, and J. 8. Engel, &istribthtis~z and Behavior of T~ititcrn in -the Coolant-Salt Technology Facilityy, BRNL/TM-5759 (April 1977). N. M. Greene, Union Carbide Corporation, personal esmmunicatisn to W. A. Woades, Qak Ridge National Laboratory, September 1977. J. Re Might Union Carbide Corporation, pers~nal c~mmuni~ation to We A. Rkoades, Oak Ridge National Laboratory, June 1978. E
. ... . .,.,.,.,.,. . , i.rc- q.... , 141 16. J. R. Knight, Union Carbide Corporation, personal communication to W. A. Rhoades, Oak Ridge National Laboratory, June 11978. $7. Argonne National Laboratory, Reactor Phpics Csmtants, AMJ-580O (July 1963). 19. W. R. Grimes, "Molten-Salt Reactor Chemistry," Nuel. Appl. Tech~101. %, 137 (February 1970). 20. W. R. Grimes et al., "Fuel and Coolant Chemistry," chap. 5, p. 95 in ?%e Devetogment Status of Molten-Salt Breeders, 08K-4812 (August 1972). 22. P. N. Haubenreich and J. R. Engel, "Experience with the Holten-Salt Reactor Experiment," Nucz. Apple TechnsZ. 8, 118 (February 1970). 24. S. Cantor, Density and Viscosity of Sevarat Molten Fluco~ide Mite- tupeg, ORNE/TM-4308 (March 1973). 25. C. F. Baes, Jr., p. 617 in "Symposium on Reprosessing sf Nuelear Fuels," ed. by P. Chiotti, vol. 15 of fluetea? MetatZurgy, USAEC- COW-690801 (1969). 26. C. F. Baes, Jr., "The Chemistry and Themodynamics of Molten-Salt Reactor Fuels," J. .VucZ. Mat. 51, 149 (1974). 27. C. E. Bamberger, R. G. ROSS, and C. F. Baes, Jr., "'Phe Oxide Chemis- try of Plutonium in Molten Fluorides and the Free Energy of Forma- tion of PuF3 and PuP,,"J. Inorg. Nuel. &ern. 33, 776 (11971). 2%. J. K. Dawson et al., "The Preparation and Some Properties of Plutonium ~luorides," J. €%em. A~oe. % 55% (1954). 29. C. E. Bamberger et al., "Absenee of an Effect of Oxide on the Solubility and the Absorption Spectra of PuF3 in Molten EiF-BeF2-ThP4 and the Instability of B~U~OR~UIII (111) Oxyflu~rides," J. Inorg. Nucz. Chem. %3, 3591 (1971). 38. '*Molten Salt Reactor Concept 911 Quar-terZy Reg~p?-t fop tge~iod Ending Jdy 39, 1971 Atomic Energy Commission, Bombay, India, NP-119145.
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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.
Page 21 and 22:
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
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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
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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
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 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: 139 The authors want to acknowledge
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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