TESTING THE FILTERING PROCESS FOR SPENT ZINC MELT AFTER REMOVAL OF FUEL CLADDING WITH THE BOR-60 REACTOR SNF NITRIDE

Verification results of filtering process effectiveness of a zinc melt obtained after solving a fuel element cladding of the BOR-60 reactor with nitride spent nuclear fuel (SNF) in it are presented. The test was carried out in a laboratory apparatus for cleaning the zinc melt from slurries of fission products, fuel and intermetallic particles in a hot cell. A filter material selection for the filter elements is discussed. The possibility of using the filtering operation in compliance with a ratio of structural materials to zinc for regeneration of zinc after removal in it the fuel element cladding.