Cost of Processing Fuel from a Molten Salt, Fusion/Fission, Hybrid Reactor Blanket

Abstract

A conceptual flowsheet was prepared for continuous processing of molten salt used as the blanket material for breeding tritium and fissile material (²³³U) in a fusion/fission hybrid reactor. The salt, which has a melting point of ∼530°C, was 70 mol % LiF, 12 mol % BeF₂, and 18 mol % ThF₄. The hybrid reactor generates 3000 MWe, and the blanket contains 65 m³ of the breeding salt.