FIELD: nuclear power engineering.
SUBSTANCE: invention relates to nuclear power engineering and can be used to obtain fuel salt based on lithium and beryllium fluorides, intended for introduction into the circuit of a power unit of molten-salt reactors. The method includes the use of a mixture containing ammonium tetrafluoroberyllate and lithium fluoride, taken in an amount corresponding to the eutectic composition of the resulting salt, heated in an argon flow to a temperature of 230-250°C, maintained until complete decomposition of ammonium tetrafluoroberyllate, then the heating temperature of the mixture is raised above the melting point of Li2BeF4, but not higher than 530°C. Next, the mixture is kept until a fuel salt is obtained, which is cooled in a stream of argon to room temperature.
EFFECT: invention provides the possibility of obtaining fuel salt for power units of molten-salt reactors without the need to purge gaseous HF with excess.
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Authors
Dates
2022-08-29—Published
2022-01-24—Filed