2:45 PM - 3:00 PM
[3O10] Tritium permeation and recovery from molten salt Flinabe blanket of fusion reactor
Keywords:tritium, blanket, molten salt, permeation, recovery
Flinabe moleten salt (LiF+NaF+BeF2 fluoride mixture) is one of the most promising liquid balnket candidates. Previously, its melting point of an equimolar mixture is around 300oC, physical or chemical properties are near to those of Li2BeF4, and hydrogen isotope permeability through it is also near to that of Flibe. In the present study, experimental conditions of hydrogen permeation through Flinabe are extended in the range of 10 to 106 Pa, and it is confirmed that the permeability dependence on pressure varies from the linear of Flinabe diffusion limiting to the square root of Monel alloy diffusion limiting. In addition diffusion time delay due to hydrogen absorption inside Ti particles included in Flinabe is effective to surppress hydrogen permeation in earier time. Effective tritium recovery from the molten salt reactor of FFHR is investigated.