Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor

Abstract

Abstract FLIBE (LiF–BeF2) is both a nuclear reactor coolant and a solvent for fertile or fissile materials. FLIBE can also dissolve a variety of fissile and fertile materials such as uranium, thorium and plutonium and has the ability to serve as liquid fuel for molten salt reactors (MSRs). It’s very high thermal capacity and chemical stability are among its other valuable properties. In addition, the low atomic weights of lithium, beryllium and to a lesser extent fluorine make FLIBE an effective neutron moderator. In this study, cross-section values were determined by using various level density models (constant temperature + Fermi gas, back-shifted Fermi gas, generalized superfluid, microscopic level density models) for reactions of 19F(n, α)16N, 19F(n, p)19O, 35Cl(n, α)32P, 35Cl(n, p)35S and 79Br(n, α)76As, 79Br(n, p)79Se, 127I(n, α)124Sb, 127I(n, p)127Te using TALYS 1.95 code and these datas are compared with the values in the EXFOR database.