2022 Annual Meeting

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Oral presentation

VI. Fusion Energy Engineering » 601-3 Tritium Science and Technology (Fuel Recovery and Refining, Measurement, Iisotope Effect, Safe Handling)

[2L08-12] Tritium Engineering

Thu. Mar 17, 2022 2:45 PM - 4:15 PM Room L

Chair: Yasuhisa Oya (Shizuoka Univ.)

3:15 PM - 3:30 PM

[2L10] Tritium release behavior from neutron-irradiated molten salt FLiNaBe

*Kazunari Katayama1, Kaito Kubo1, Toru Ichikawa1, Akito Ipponsugi1, Makoto Oya1 (1. Kyushu Univ.)

Keywords:Tritium, Molten salt, FLiNaBe, Ti, Liquid blanket

For the purpose of understanding the tritium release behavior from the molten salt FLiNaBe, which is a candidate material for tritium breeder and coolant in the liquid blanket of fusion reactors, we observed the tritium release behavior by heating from the FLiNaBe irradiated with neutrons in the Kyoto University Research Reactor. A cold trap and two bubblers installed a copper oxide bed between them were set at the outlet of a reaction tube, and the amounts of HTO, TF, and HT released were evaluated. The tritium release behavior was also observed for the FLiNaBe sample to which Ti was added for the purpose of increasing the hydrogen storage capacity. Based on these results, the effect of adding Ti on tritium behavior will be discussed.