METHOD OF CLEANING SPENT FUEL SALT BASED ON LIF-NAF-KF EUTECTIC MIXTURE Russian patent published in 2025 - IPC C01G43/25 C01F17/259 G21C19/48 G21F9/28 C01D3/14 

FIELD: performing operations.

SUBSTANCE: invention relates to processing of spent fuel salt of molten-salt reactors intended for transmutation of minor actinides, and can be used for cleaning spent fuel salt based on eutectic mixture of lithium, sodium and potassium fluorides (LiF-NaF-KF) from fissile materials and fission products accumulated during reactor operation. Method involves introduction of spent fuel salt based on eutectic mixture LiF-NaF-KF into melt at temperature 750 °C of the melt of an equimolar mixture of LiF-Li₂O. First, the melt is introduced into the purified melt in amount of 115 % of the stoichiometric amount required for deposition of uranium (IV) oxide from the spent fuel salt melt. Further, precipitated uranium (IV) oxide is removed from the melt, and then said melt is added in amount of 120 % of the stoichiometric amount required for deposition of rare-earth metal oxyfluorides from the melt.

EFFECT: separate sedimentation of fissile materials suitable for further use in composition of new fuel salt from fission products, which are radioactive wastes.

1 cl, 1 dwg, 1 ex