FIELD: chemistry.
SUBSTANCE: disclosed method includes autoclave processing of a nitrate solution of spent carbide nuclear fuel. During said processing, zirconium molybdate, which partially captures plutonium, is precipitated. The molybdenum-containing precipitate obtained as a result of autoclave processing undergoes re-precipitation via dissolution thereof in the presence of a decomposable complexon. Further, precipitation is repeated while decomposing the complexon and returning the secondary mother solution to the spent nuclear fuel dissolution step.
EFFECT: obtaining spent carbide nuclear fuel solutions, including spent mixed uranium-plutonium carbide fuel from fast neutron reactors, which are resistant to secondary precipitation and are suitable for actinide extraction.
8 cl, 7 ex
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