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

Abstract

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.