Fuel Salt for the Molten-Salt Reactor
| Autor: | A. A. Rzheutskii, S. A. Mel’nikov, A. A. Mikhalichenko, L. I. Ponomarev, M. B. Seregin, L. P. Zagorets, R. N. Manuilov, A. P. Parshin |
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| Rok vydání: | 2013 |
| Předmět: |
chemistry.chemical_classification
Materials science Molten salt reactor Salt (chemistry) Fuel element failure law.invention chemistry.chemical_compound Nuclear Energy and Engineering chemistry Chemical engineering Nuclear reactor core law Solubility Fluoride Liquid fluoride thorium reactor Eutectic system |
| Zdroj: | Atomic Energy. 115:5-10 |
| ISSN: | 1573-8205 1063-4258 |
| DOI: | 10.1007/s10512-013-9739-2 |
| Popis: | 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. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
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