Np, Am, Cm Transmutation in Different Types of Reactors

Abstract

Different approaches to the transmutation of Np, Am, and Cm in molten-salt reactors are compared: based on the eutectics LiF–NaF–KF (BZhSR), LiF–NaF–BeF₂ (MOSART), and the salt LiF–BeF₂ (ZhSR-S). In addition the efficiency of transmutation in a BREST-1200 type fast reactor is evaluated. It is shown that the highest possible transmutation efficiency can be realized in a reactor based on the salt LiF–NaF–KF (~306 kg/yr per 1 GW(t)). The results show that further study of the physical and chemical properties of LiF–NaF–KF is warranted, specifically, a study of the solubility of a fuel composition with fission products and an investigation of the possibility of developing a reactor with a fast neutron spectrum on the basis of this salt.