Article ID Journal Published Year Pages File Type
7967806 Journal of Nuclear Materials 2014 11 Pages PDF
Abstract
The present study describes the full thermodynamic assessment of the LiF-NaF-BeF2-ThF4-UF4 system which is one of the key systems considered for a molten salt reactor fuel. The work is an extension of the previously assessed LiF-NaF-ThF4-UF4 system with addition of BeF2 which is characterized by very low neutron capture cross section and a relatively low melting point. To extend the database the binary BeF2-ThF4 and BeF2-UF4 systems were optimized and the novel data were used for the thermodynamic assessment of BeF2 containing ternary systems for which experimental data exist in the literature. The obtained database is used to optimize the molten salt reactor fuel composition and to assess its properties with the emphasis on the melting behaviour.
Related Topics
Physical Sciences and Engineering Energy Nuclear Energy and Engineering
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