FIELD: chemistry.
SUBSTANCE: present invention relates to chemical and radiochemical industry and can be used for recycling spent nuclear fuel, mainly dispersion fuel elements with compositions (cermets) of the type Be - Ube13, Be - UO2, and returning enriched uranium into the fuel cycle, extracting (recycling) uranium and beryllium from waste products of uranium-beryllium compositions. In the method of processing spent uranium-beryllium nuclear fuel, spent fuel elements and fuel assemblies are broken down to pieces, sunk into water and dissolved through addition of gaseous hydrogen fluoride into the solution. After completion of the dissolution process, solid parts are separated and pulp is separated from beryllium fluoride solution and washed. The pulp is heated and treated with steam. If necessary, the obtained uranium dioxide undergoes further purification.
EFFECT: invention simplifies the method of processing spent nuclear fuel, mainly compositions of the type Be - Ube13, Be - UO2, and increases safety of carrying out the process as well.
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Authors
Dates
2009-05-27—Published
2007-07-30—Filed