Authors & Affiliations
Kriachko M.V., Khokhlov G.N.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Khokhlov G.N. – Senior Researcher, A.I. Leypunsky Institute for Physics and Power Engineering.
One of the main tasks of ensuring radiation safety of the fuel cycle of a fast neutron reactor is the problem of safe handling of fuel assemblies. In the case of a closed nuclear fuel cycle with fast reactors, fuel assemblies for reactor loading will be produced from regenerated uranium and plutonium separated from SNF during processing.
Radiation characteristics of SNF, such as activity, residual heat release and gamma radiation intensity, are determined mainly by fission products.
At the same time, in the case of the use of technologies with incomplete purification of the regenerate from the fission products in SNFC, the fission products remaining in the regenerate can significantly complicate the treatment of fresh fuel assemblies.
In this paper, the optimization of the requirements for SNF reprocessing technology from the point of view of radiation characteristics is considered.
spent nuclear fuel, pyrochemical SNF reprocessing, hydrometallurgical SNF reprocessing, regenerated uranium, regenerated plutonium
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