RADIOACTIVE WASTE MANAGEMENT FROM REPROCESSING OF NITRIDE SPENT FUEL FROM FAST REACTORS

摘要

In Russia under development are inherently safe fast reactors to be fuelled with mixed U-Pu nitrides. Reprocessing spent nuclear fuel of those reactors is assumed to be carried out by non-aqueous processes. The final products of reprocessing shall be fractions of uranium, plu-tonium and minor actinides which will be used to manufacture mixed fuel for fresh loads of the reactor as well as fractions of fission products to be conditioned and long-time stored or transmuted in reactor. Fractions feature very high activities and intensive heat releases. The paper presents general flow layouts of radioactive waste management arising at a designed nuclear power plant comprising a demonstration fast reactor BREST-OD-300 and a semi -commercial complex for reprocessing spent fuel from this reactor. All the schematics presented are now under development.