LiF–NaF–KF Eutectic Based Fast Molten-Salt Reactor as Np, Am, Cm Transmuter


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Аннотация

The issues of Np, Am, Cm recycling in a BZhSR molten-salt reactor with a fast neutron spectrum based on LiF–NaF–KF eutectic are examined. The results of a comparative analysis of the efficacy of transmutation for different BZhSR fuel compositions and core volume are reported. It is shown that BZhSR with an initial load of enriched uranium and Np, Am, Cm fl uorides makes it possible to transmute ~1 ton/yr Np, Am, Cm on average over 50 years of operation at 1650 MW(t). The advantage of the chosen arrangement is the capability of Np, Am, Cm replenishment without adding additional enriched uranium even after the first run with duration 300 EFPD.

Авторлар туралы

L. Ponomarev

Bochvar High-Technology Research Institute of Inorganic Materials (VNIINM)

Email: m.n.belonogov@vniitf.ru
Ресей, Moscow

M. Belonogov

Russian Federal Nuclear Center — Zababakhin All-Russia Research Institute of Technical Physics (VNIITF)

Хат алмасуға жауапты Автор.
Email: m.n.belonogov@vniitf.ru
Ресей, Snezhinsk, Chelyabinsk, Oblast

I. Volkov

Russian Federal Nuclear Center — Zababakhin All-Russia Research Institute of Technical Physics (VNIITF)

Email: m.n.belonogov@vniitf.ru
Ресей, Snezhinsk, Chelyabinsk, Oblast

V. Simonenko

Russian Federal Nuclear Center — Zababakhin All-Russia Research Institute of Technical Physics (VNIITF)

Email: m.n.belonogov@vniitf.ru
Ресей, Snezhinsk, Chelyabinsk, Oblast

U. Sheremet’eva

Russian Federal Nuclear Center — Zababakhin All-Russia Research Institute of Technical Physics (VNIITF)

Email: m.n.belonogov@vniitf.ru
Ресей, Snezhinsk, Chelyabinsk, Oblast

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