Abstract

Currently, nuclear society has recognized that further development of Russian nuclear power industry will be carried out under the two-component framework represented with thermal and fast reactors operating within the total closed fuel cycle. Several scenarios of the nuclear fuel cycle closure within Russian two-component nuclear power system (NPS) have been currently discussed among the industry specialists. These scenarios are based on various philosophies of the NFC closure (centralized NFC closed by thermal and fast reactors fuel or station NFC for closure of the fuel cycle of BREST reactors only), various fast reactor technologies and various types of the fuel used: UOX/MOX or mixed nitride U-Pu. The key difference is in different understanding of fast reactors role in NPS fuel cycle closure. This results in varying requirements to fast reactors and the terms of implementation of such requirements. This report focuses on the role of fast sodium reactors as a system-forming component of the future two-component nuclear power system operating within the total fuel cycle with thermal reactors.

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