Cost of Processing Fuel from a Molten Salt, Fusion/Fission, Hybrid Reactor Blanket
Fusion Science and Technology / Volume 8 / Number 2P2 / September 1985 / Pages 2113-2120
Blanket and Process Engineering / Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) / dx.doi.org/10.13182/FST85-A24596
Articles are hosted by Taylor and Francis Online.
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.
