A unique method has been developed for removal of cans of spent fuel assemblies of thermal or fast reactors by dissolution of the cans in liquid metal.

The proposed method can be used to remove fuel cladding made of special steels or zirconium alloys (VVER-1000, BREST and BN reactors).

The proposed method makes processing of radioactive materials more effcient and technologically effective.

The method has been developed in collaboration with OAO SverdNIIhimmash and the Research and Design Institute for Power Engineering (FGUP NIKIET).

ADVANTAGES

• The fuel can be separated from structural materials without cutting the assembly. Hence, reprocessing is considerably simplified and is less costly.

• The fuel cladding can be opened with little or no loss of both nitride and oxide fuels.

• Remainders of fuel assemblies can be compacted. This is important for both reprocessing arrangements and provision of conditions for disposal and storage of waste.