Fuel Salt for the Molten-Salt Reactor

descriptionPublicationkeyboard_double_arrow_right Article 20 Oct 2013 English Publisher:Springer Science and Business Media LLCJournal:Atomic Energy, volume 115, pages 5-10 (issn: 1063-4258, eissn: 1573-8205,

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Authors: L. I. Ponomarev; M. B. Seregin; A. P. Parshin; S. A. Mel’nikov; A. A. Mikhalichenko; L. P. Zagorets; R. N. Manuilov; +1 Authors

doi: 10.1007/s10512-013-9739-2

Fuel Salt for the Molten-Salt Reactor

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Abstract

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.

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Kurchatov Institute
Russian Federation

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