METHOD OF PROCESSING NITRIDE SNF IN MOLTEN SALT WITH EXTRACTION OF THE TARGET COMPONENT USING A PRECIPITATOR Russian patent published in 2022 - IPC G21C19/42 

Abstract RU 2766563 C2

FIELD: chemical or physical processes.

SUBSTANCE: invention relates to a method for processing of spent nuclear fuel (SNF). Proposed method comprises dissolving nitride spent nuclear fuel in molten salt and separating actinides by precipitation by adding lithium nitride to molten salt. Separation of actinides from molten salt is carried out by adding precipitant at 500–750 °C and subsequent distillation of the salt phase at temperature of 900–1,100 °C and pressure 1×10−3–1×10−2 mm Hg. Lithium nitride is used as a precipitation agent.

EFFECT: invention makes it possible to create conditions for extraction of actinides from salt melt after dissolution of spent nitride fuel.

1 cl, 1 ex

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RU 2 766 563 C2

Authors

Selyavskij Vadim Yurevich

Ushakov Dmitrij Aleksandrovich

Zhitkov Aleksandr Sergeevich

Ovchenkov Sergej Gennadevich

Kharitonov Artem Olegovich

Dates

2022-03-15Published

2020-08-16Filed