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Electrical conductivity of molten mixtures of uranium, thorium, beryllium, and sodium fluorides

Journal Article · · J. Appl. Chem. USSR (Engl. Transl.); (United States)
OSTI ID:5296428
In discussions of the composition of fuels for molten-salt nuclear reactors it has been noted that possible fuel compositions may consist of uranium and thorium fluorides mixed with diluent salts such as the fluorides of lithium, sodium, beryllium, and zirconium. However, the properties of such salt compositions have not been studied sufficiently; in particular, there are no data in the literature on the conductivities of three- and four-component salt melts. In this paper we report the results of a study of the dependence of the conductivity of melts in the system NaF-ThF/sub 4/-BeF/sub 2/, and in the region of low-melting compositions of the four-component system NaF-ThF/sub 4/-BeF/sub 2/-UF/sub 4/, on temperature and concentration.
Research Organization:
Ural Polytechnic Inst., USSR
OSTI ID:
5296428
Journal Information:
J. Appl. Chem. USSR (Engl. Transl.); (United States), Journal Name: J. Appl. Chem. USSR (Engl. Transl.); (United States) Vol. 54:7; ISSN JAPUA
Country of Publication:
United States
Language:
English

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