5.10 - Material Performance in Molten Salts

Comprehensive Nuclear Materials: Volume 1-5

Volumn 1-5, Issue , 2012, Pages 221-250

  Ignatiev, V ^a   Surenkov, A ^a  

^a KURCHATOV INSTITUTE   (Russian Federation)

Author keywords

Alloys; Brittleness; Chromium alloys; Coolants; Corrosion; Embrittlement; Expansion; Fast neutrons; Fuel salts; Graphite; Hastelloy; Mixtures; Molten salt fluorides; Molten salt reactors; Molybdenum alloys; Nickel; Porosity; Radiation effects; Redox potential; Stability; Tellurium

Indexed keywords

EID: 84878618459     PISSN: None     EISSN: None     Source Type: Book    
DOI: 10.1016/B978-0-08-056033-5.00098-7     Document Type: Chapter

References (95)

1. V. Ignatiev, O. Feynberg, V. Smirnov, A. Tataurov, G. Vanukova and R. Zakirov (2005) Characteristics of molten salt actinide recycler and transmuter system. Proceedings of International Conference on Emerging Nuclear Energy Systems, Brussels, Belgium, Aug 21-26 paper ICQ064
2. C.W. Forsberg, C. Lebrun, E. Merlet-Lucotte, C. Renault and V. Ignatiev (2007) Revue Generale Nucleaire 4 63-71.
3. C.W. Forsberg, et al. (2008) Design options for the advanced high-temperature reactor. Proceedings of International Congress on Advances in Nuclear Power Plants, Anaheim, CA, Jun 8-12
4. S. Delpech, et al. (2009) J. Fluorine Chem. 130(1), 11-17.
5. C. Renault, et al. (2009) European molten salt reactor. Proceedings of Seventh European Commission Conference on Euroatom Research and Training in Reactor Systems, Prague, Czech Republic, Jun 22-24
6. A.V. Chechetkin (1962) High Temperature Coolants. Moscow, USSR: Gosenergoizdat
7. P.F. Tortorelli and J.H. DeVan (1982) Thermal convection loop study of the corrosion of Fe-Ni-Cr alloys by molten NaNO3-KNO3. Oak Ridge, TN: ORNL ORNL/TM-8298
8. R.W. Mar, et al. (1983) The use of molten nitrate salts in high temperature energy conversion systems. Proceedings of First International Symposium on Molten Salt Chemistry and Technology, Kyoto, Japan, Apr 20-22 285-288.
9. M. Taube (1978) Fast Reactors Using Molten Chloride Salts as Fuel. Switzerland: Wurenlingen
10. L.L. Migai and T.A. Taritsina (1988) Corrosion Resistance of Structural Materials in Halides and their Mixtures. Moscow, USSR: Metallurgy
11. M.W. Rosenthal, et al. (1970) Nucl. Appl. Technol. 8(2), 107-118.
12. E.S. Bettis, et al. (1957) Nucl. Sci. Eng. 2(6), 804-812.
13. W.D. Manly, et al. (1957) ARE-metallurgical aspects. Oak Ridge, TN: ORNL ORNL-2349
14. W.B. Cottrell (1958) Disassembly and postoperative examination of the aircraft reactor experiment. Oak Ridge, TN: ORNL ORNL-1868
15. P.N. Haubenreich and J.R. Engel (1970) Nucl. Appl. Technol. 8(2), 107-140.
16. E.S. Bettis and R.C. Robertson (1970) Nucl. Appl. Technol. 8(2), 190.
17. M.W. Rosenthal, P.N. Haubenreich and R.B. Briggs (1972) Development status of molten salt breeder reactors Oak Ridge, TN: ORNL 250. ORNL-4812
18. K. Furukava, et al. (1990) J. Nucl. Sci. Technol. 27 1157-1178.
19. V.M. Novikov, V.V. Ignatiev, V.I. Fedulov and V.N. Cherednikov (1990) Molten Salt Reactors: Perspectives and Problems. Moscow, USSR: Energoatomizdat
20. V.V. Ignatiev, V.M. Novikov, A.I. Surenkov and V.I. Fedulov (1993) The state of the problem on materials as applied to molten-salt reactor: Problems and ways of solution. Moscow, USSR: Institute of Atomic Energy Preprint IAE-5678/11
21. Grope detravail CEA-EDF (1983) Materiax metalliques RSF: Synfese des etudes realisees entre 1973 et. Rapport EDF HT/12/77/83; dossier materiax metalliques: Paris, France, 1983
22. D. Lecarpentier and J. Vergnes (2002) Nucl. Eng. Des. 216 43-67.
23. C.W. Forsberg, P.F. Peterson and P.S. Pickard (2003) Nucl. Technol. 144 289-302.
24. C.W. Forsberg, et al. (2005) Practical aspects of liquid-salt-cooled fast-neutron reactors. Proceedings of ICAPP’05, Seoul, Korea, May 15-19 paper 5643
25. R. Petroski, P. Hejzlar and N.E. Todreas (2009) Nucl. Eng. Des doi:10.1016/j.nucengdes.2009.07.012
26. D.F. Williams, L.M. Toth and K.T. Clarno (2006) Assessment of candidate molten salt coolants for the advanced high-temperature reactor. Oak Ridge, TN: ORNL ORNL/TM-2006/12
27. R.E. Thoma (Ed.) (1959) Phase diagrams of nuclear reactor materials Oak Ridge, TN: ORNL ORNL-2548
28. C.J. Barton and R.A. Strehlow (1961) J. Inorg. Nucl. Chem. 18 143.
29. Atomic Energy Commission. Molten salt breeder reactor concept Quarterly report for period ending July 21, NP-19145; Bombay, India, 1971.
30. C.E. Bamberger, R.S. Ross and C.F. Baes (1971) J. Inorg. Nucl. Chem. 33 3591-3594.
31. W.T. Ward, R.A. Strehlow, W.R. Grimes and G.M. Watson (1960) J. Chem. Eng. 5(2), 137-142.
32. C.J. Barton (1960) J. Phys. Chem. 64 306-309.
33. V. Ignatiev, Y. Golovatov, A. Merzlyakov, A. Panov and V. Subbotin (2006) Atom. Energy 101(5), 364-372.
34. D.F. Williams (2006) Assessment of candidate molten salt coolants for the NGNP/NHI heat-transfer loop. Oak Ridge, TN: ORNL ORNL/TM-2006/69
35. W.D. Manly, L.S. Richardson and D.E. Vreeland (1960) Prog. Nucl. Energy 2(4), 164-179.
36. J.H. DeVan and R.B. Evans III. (1962) Corrosion behavior of reactor materials in fluoride salt mixtures. Oak Ridge, TN: ORNL ORNL/TM-328
37. G.M. Adamson, R.S. Crouse and W.D. Manly (1961) Interim report on corrosion by zirconium-base fluorides. Oak Ridge, TN: ORNL ORNL-2338
38. J.H. De Van and R.B. Evans (1962) Proceedings of the Conference on Corrosion of Reactor Materials, Jun 4-8, 1962 Vienna, Austria: IAEA 557-579.
39. W.R. Grimes (1970) Nucl. Appl. Technol. 8(2), 137-155.
40. C.F. Baes (1974) J. Nucl. Mater. 51(1), 149.
41. R.B. Evans III, J.H. DeVan and G.M. Watson (1960) Self-diffusion of chromium in nickel-base alloys. Oak Ridge, TN: ORNL ORNL-2982
42. J.W. Koger (1972) Alloy compatibility with LiF-BeF2 salts containing ThF4 and UF4. Oak Ridge, TN: ORNL ORNL-TM-4286
43. J.R. Keiser, et al. (1975) Salt corrosion studies Oak Ridge, TN: ORNL 91-97. ORNL-5078
44. J.W. Koger (1973) Forced-convection loop corrosion studies Oak Ridge, TN: ORNL 135-137. Huntley WR and ORNL-4832
45. C.E. Bamberger and C.F. Baes (1973) Corrosion of Hastelloy N by fluoroborate melts Oak Ridge, TN: ORNL 44-45. ORNL-4832
46. J.R. Keiser (1977) Compatibility studies of potential molten-salt breeder reactor materials in molten fluoride salts. Oak Ridge, TN: ORNL ORNL-TM-5783
47. V. Ignatiev, V. Fedulov, V. Novikov and A. Surenkov (1981) Voprocy Atomnoi Nauki i Tehkniki: Atomno - Vodorodnaya Energetika i Tehnologiya 3(10), 74-76.
48. H. De Van, J.R. Distefano, W.P. Eartherly, J.R. Keiser and R.L. Klueh (1993) Materials considerations for molten salt accelerator based plutonium conversion system. Proceedings of the Global’93 International Conference, Las Vegas
49. L.E. McNeese (1974) Program plan for development of molten-salt breeder reactors Oak Ridge, TN: ORNL 5-46. ORNL-5018
50. L. Maya (1976) J. Inorg. Chem. 15(9), 2179-2184.
51. G.T. Mays (1977) Distribution and behavior of tritium in the coolant-salt technology facility. Oak Ridge, TN: ORNL ORNL/TM-5759
52. R.B. Briggs (1962) Molten salt reactor program semiannual progress report for period ending February 28. Oak Ridge, TN: ORNL ORNL-3282
53. J.H. Shaffer (1964) Preparation of MSRE fuel, coolant and flush salt Oak Ridge, TN: ORNL 288-302. ORNL-3708
54. R.B. Briggs (1965) Molten salt reactor program semiannual progress report for period ending February 28 Oak Ridge, TN: ORNL 121-168. ORNL-3812
55. J.H. Shaffer (1971) Preparation and handling of salt mixtures for the molten salt reactor experiment. Oak Ridge, TN: ORNL ORNL-4616
56. V.L. Cherginets (2001) Handbook of Solvents Toronto, Canada: Chemical Technology 633-635. Chap. 10.3
57. V.L. Cherginets and T.P. Rebrova (1999) Electrochim. Acta 45(3), 469-476.
58. J.R. Engel, H.F. Bauman, J.F. Dearing, W.R. Grimes, E.H. McCoy and W.A. Rhoades (1979) Development status and potential program for development of proliferation resistance molten salt reactor. Oak Ridge, TN: ORNL ORNL-TM-6415
59. O.R. Harries (1966) J. Br. Nucl. Soc. 5 74.
60. H.E. Mc Coy and T.K. Roche (1975) Post irradiation creep properties of modified Hastelloy N Oak Ridge, TN: ORNL 82-84. ORNL-5078
61. H.E. Mc Coy, et al. (1972) Intergranular cracking of structural materials exposed to fuel salt Oak Ridge, TN: ORNL 109-144. ORNL-4782
62. H.E. Mc Coy, et al. (1972) Intergranular cracking of structural materials exposed to fuel salt Oak Ridge, TN: ORNL 63-76. ORNL-4832
63. H.E. Mc Coy, et al. (1972) Metallographic examination of samples exposed to tellurium-containing environments Oak Ridge, TN: ORNL 108-113. ORNL-5078
64. H.E. Mc Coy, et al. (1976) Development of modified Hastelloy N Oak Ridge, TN: ORNL 42-162. ORNL-5132
65. H.E. Mc Coy, et al. (1978) Status of materials development for molten salt reactors. Oak Ridge, TN: ORNL ORNL-TM-5920
66. J.R. Keiser (1977) Status of tellurium-Hastelloy N studies in molten fluoride salts. Oak Ridge, TN: ORNL ORNL-TM-6002
67. V. Ignatiev, V. Fedulov, V. Novikov and A. Surenkov (1989) Voprocy Atomnoi Nauki i Tehkniki: Atomno - Vodorodnaya Energetika i Tehnologiya 3 23-25.
68. V.V. Ignatiev, et al. (2006) Experience with alloys compatibility with fuel and coolant salts and their application to molten salt actinide recycler and transmuter. Proceedings of International Congress on Advances in Nuclear Power Plants, Reno, NV, Jun 4-8
69. V.V. Ignatiev, et al. (2006) Atom. Energy 101(4), 278-285.
70. V.V. Ignatiev, et al. (2008) Nucl. Technol. 164(1), 130-142.
71. C.R. Tripton (1960) The Reactor Handbook Vol. 3 464.
72. A.P. Litman, et al. (1961) Corrosion associated with fluorination in the ORNL fluoride volatility process. Oak Ridge, TN: ORNL ORNL-2832
73. L. Hags, et al. (1968) Comparative tests of L nickel, D nickel, Hastelloy B and INOR-1 Oak Ridge: TN: ORNL 49-52. ORNL-5924
74. O.B. Cavin, et al. (1971) Molten salt reactor program semiannual report for period ending August 31 Oak Ridge, TN: ORNL 173-176. ORNL-4728
75. M.R. Bennett (1976) Molten salt reactor program semiannual report for period ending February 29 Oak Ridge, TN: ORNL 170. ORNL-5132
76. R.M. Counce (1975) Molten salt reactor program semiannual report for period ending August 31 Oak Ridge, TN: ORNL 157. ORNL-5078
77. C.H. Brown, et al. (1976) Measurement of mass transfer coefficients in a mechanically agitated, nondispersing contactor operating with a molten mixture of LiF-BeF2-ThF4 and molten bismuth. Oak Ridge, TN: ORNL ORNL-5143
78. H.C. Savage, et al. (1977) Engineering tests of metal transfer process for extraction of rare-earth fission products from a molten salt breeder reactor fuel salt. Oak Ridge, TN: ORNL ORNL-5176
79. H. Shimotake, et al. (1967) Trans. Am. Nucl. Soc. 10 141-142.
80. J.W. Siefert, et al. (1961) Corrosion 17(10), 75-78.
81. O.B. Cavin, et al. (1972) Molten salt reactor program semiannual report for period ending February 29 Oak Ridge, TN: ORNL 198. ORNL-4782
82. D.T. Ingersoll, et al. (2004) Status of preconceptual design of the advanced high-temperature reactor. Oak Ridge, TN: ORNL ORNL/TM-2004/104
83. W.H. Jordan, et al. (1956) Aircraft nuclear propulsion project quarterly progress report for period ending June 10 Oak Ridge, TN: ORNL 95. ORNL-2106
84. W.H. Jordan, et al. (1956) Aircraft nuclear propulsion project quarterly progress report for period ending September 10 Oak Ridge, TN: ORNL 107. ORNL-2157
85. W.H. Jordan, et al. (1956) Aircraft nuclear propulsion project quarterly progress report for period ending December 31 Oak Ridge, TN: ORNL 125. ORNL-2221
86. W.H. Jordan, et al. (1956) Aircraft nuclear propulsion project quarterly progress report for period ending September 10 Oak Ridge, TN: ORNL 145. ORNL-2157
87. M. Kondo, et al. (2009) Fusion Eng. Des. 84(7-11), 1081-1085.
88. L.C. Olson, et al. (2009) J. Fluorine Chem. 130 62-73.
89. J.R. Keiser, et al. (1977) The corrosion of type 316 stainless steel to Li2BeF4 ORNL/TM-5782. Oak Ridge, TN: ORNL
90. G.D. Del Cul, et al. (2002) Redox potential of novel electrochemical buffers useful for corrosion prevention in molten fluorides. Proceedings of the Thirteenth International Symposium on Molten Salts Held within the 201st Meeting of the Electrochemical Society, Philadelphia, PA, May 12-17
91. C. Brown, et al. (1994) Nucl. Eng. 35(4), 122-128.
92. Y. Konobeev and G. Birzhevoi (2004) Atom. Energy 96(5), 365-373.
93. Generation IV Nuclear Energy Research Advisory Committee (2002) Generation IV roadmap: Description of candidate liquid-metal-cooled reactor systems. Washington DC: Department of Energy GIF-017-00
94. K. Bakker, et al. (2004) Nucl. Technol. 146 325-331.
95. H. Susskind, et al. (1960) Corrosion studies for a fused salt-liquid metal extraction process for the liquid metal fuel reactor. Brookhaven, NY: Brookhaven National Laboratory BNL-585