Fuel Salt for the Molten-Salt Reactor

The solubility of Th, U, Ce, La, and Pr in melted salt 45LiF–12NaF–43KF, which supports a fast neutron spectrum for the molten-salt reactor, is found experimentally to be high in the interval 550–700°C. On the basis of an analysis of the physicochemical and nuclear-physical properties of different f...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2013-11, Vol.115 (1), p.5-10
Main Authors: Ponomarev, L. I., Seregin, M. B., Parshin, A. P., Mel’nikov, S. A., Mikhalichenko, A. A., Zagorets, L. P., Manuilov, R. N., Rzheutskii, A. A.
Format: Article
Language:English
Subjects:
Corrosion
Fluorides
Hadrons
Heat conductivity
Heavy Ions
Nuclear Chemistry
Nuclear Energy
Nuclear engineering
Nuclear fuels
Nuclear Physics
Nuclear reactors
Physical properties
Physics
Physics and Astronomy
Plutonium
Reactors
Salts
Sodium
Studies
Uranium
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Summary:The solubility of Th, U, Ce, La, and Pr in melted salt 45LiF–12NaF–43KF, which supports a fast neutron spectrum for the molten-salt reactor, is found experimentally to be high in the interval 550–700°C. On the basis of an analysis of the physicochemical and nuclear-physical properties of different fluoride salts, it is proposed that the eutectic 46.5LiF–11.5NaF–42KF be used as the fuel salt for a molten-salt fast reactor with a uranium-plutonium fuel cycle.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-013-9739-2