The Concept of Hybrid Reactor of Tokamak and Molten-salt Thorium Blanket for Producing 233 U out of Neutron Field

A concept is offered for tokamak and molten-salt thorium blanket with liquid-metal mass-exchanger which allows an uninterrupted extraction of protactinium from the blanket and its accumulation in a cascade salt trap separately from fission products. At uninterrupted extraction of protactinium from neutron field with the same rate, such a facility can become attractive for industrial production of nuclear fuel ( 233 U) from thorium. For this, it is offered to use a reduction extraction of radio-nuclides into a liquid-metal carrier (directly contacting with the molten salt) by managing RedOx potential (Fermi level) of the salt composition. Establishing Fermi level in the first cascade of molten-salt trap only for oxidizing the lanthanides allows extracting only them from the liquid-metal carrier. In the second cascade of this trap, one can extract protactinium by shifting down Fermi level at higher oxidation potential. For correct operation of the trap cascades, the lanthanides portion in the second cascade will be less than 0.01% of the first one and the portion of protactinium in the first cascade will be four orders less than in the second one.