[3O10-16] Tritium Engineering(Fuel Recycling, Isotopic Effects, Safety Handling)

[3O10] Tritium permeation and recovery from molten salt Flinabe blanket of fusion reactor

*Satoshi Fukada¹, Jun Yamashita¹, Katsuya Tsukahara¹, Kazunari Katayama¹, Jyuro Yagi², Akio Sagara² (1. Kyushu University, 2. National Institute for Fusion Science)

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 300^oC, 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.