Abstract
All advantages of nuclear power can be fully implemented only by improving existing and developing new safe types of nuclear reactors including molten salt reactors. A promising direction is the development of a closed nuclear fuel cycle with fast reactors, which includes the production of mixed uranium-plutonium fuel, reprocessing of spent nuclear fuel, and reuse (recycling) of fuel in fast-breeder reactors. The aim of this work is to examine the possibility of using molten salts as fuel in the molten salt reactors and the media for reprocessing of spent nuclear fuel, as well as the presentation of the results of the systematic studies of physicochemical properties (phase diagrams, density, viscosity, surface tension) of molten ternary mixtures of uranium halides with salt diluents. Developing a database of nuclear-physical and physicochemical properties of molten salts is necessary for their optimal application in nuclear technology.
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Vasin, B.D., Katyshev, S.F., Raspopin, S.P.: Strategy of scientific and technological progress of nuclear energy. Equip. Process Indus. 7, 11–13 (2000)
McNeese, L.E. (ed.): Program Plan for Development of Molten-Salt Breeder Reactors. ORNL, Oak Ridge (1974)
Bokavchuk, A.V., Katyshev, S.F.: Uranium chloride melts is as nuclear fuel and the environment for regeneration. In: Kharitonov, V.V. (ed.) Proceedings of the 10th International Conference on Aurorapolaris 2007. Nuclear Future: Safety, Economy and Right, pp. 349–352. MEPHI, Moscow (2007)
Katysheva, A.S., Katyshev, S.F.: Use of ionic melts in nuclear power. In: Krasnobaev, A.S. (ed.) Proceedings of the 11th International Conference on Aurorapolaris 2008. Nuclear Future: Technology, Safety and Environment, pp. 198–200 (2008)
Ignatiev, V.V., Feynberg, O.S., Zagnitko, A.V.: Molten-salt reactors: New possibilities, problems and solutions. Atom. Energy. 112(3), 135–143 (2012)
Desyatnic, V.N., Mel’nikov, Y.T., Raspopin, S.P., Sushko, V.I.: Ternary systems containing chlorides of sodium, potassium, calcium, tri- and tetrachloride of uranium. Atom. Energy. 31(6), 631–633 (1971)
Desyatnic, V.N., Katyshev, S.F., Raspopin, S.P.: Physicochemical properties of melt comprising mixtures of uranium tetrachlorides with the chlorides of alkali metals. Atom. Energy. 42(2), 108–112 (1977)
Vohmyakov, A.N., Desyatnic, V.N., Katyshev, S.F.: A study of certain physicochemical properties of melts CaCl2-CaF2-CaO. Physicochem. Stud. Metallur. Processes Collect. Papers. 2, 70–75 (1974)
Bystraj, G.P., Desyatnik, V.N.: Method of a small bridge for determination of the coefficients of the thermal conductivity of molten salts. Phys. Chem. Electrochem. Molten Salts. 220, 56 (1973)
Katyshev, S.F., Desyatnik, V.N.: Bulk and surface properties of melts NaCl-UCl3-UCl4 system. Russ. J. Phys. Chem. 54(6), 1606–1610 (1980)
Katyshev, S.F., Desyatnik, V.N.: Density and surface tension of melts KCl-UCl3-UCl4 system. Russ. J. Phys. Chem. 55(11), 2888–2892 (1981)
Katyshev, S.F., Chervinskii, Y.F., Desyatnik, V.N.: Viscosity of uranium tri- and tetrachloride melts with sodium chloride. Russ. J. Phys. Chem. 57(11), 1256–1257 (1983)
Katyshev, S.F., Chervinskii, Y.F., Desyatnik, V.N.: Density and viscosity of molten mixtures of uranium chlorides and potassium chloride. Atom. Energy. 53(2), 108–109 (1982)
Bystraj, G.P., Desyatnik, V.N., Zlokazov, V.A.: Thermal conductivity of molten uranium tetrachloride mixed with sodium chloride and potassium chloride. Atom. Energy. 36(6), 517–518 (1974)
Bystraj, G.P., Desyatnik, V.N.: Thermal conductivity of the molten mixtures of sodium chloride and potassium chloride. Atom. Mol. Phys. 44, 125–127 (1976)
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Katyshev, S., Teslyuk, L. (2018). Ionic Melts in Nuclear Power. In: Syngellakis, S., Brebbia, C. (eds) Challenges and Solutions in the Russian Energy Sector. Innovation and Discovery in Russian Science and Engineering. Springer, Cham. https://doi.org/10.1007/978-3-319-75702-5_21
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DOI: https://doi.org/10.1007/978-3-319-75702-5_21
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