2017 Fall Meeting

Presentation information

Oral presentation

V. Fusion Energy Engineering » 501-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[3O01-05] Fusion Reactor Materials (SiC, Coating Material, Molten Salt)

Fri. Sep 15, 2017 9:30 AM - 10:50 AM Room O (Seminar room 1- Frontier Research in Applied Sciences Building)

Chair:Yuji Hatano (Univ. of Toyama)

10:30 AM - 10:45 AM

[3O05] Experiment on Tritium Behavior in Molten Salt FLiNaK with AmBe Neutron Source

*Kohki Kumagai1, Teruya Tanaka1,2, Juro Yagi1,2, Takashi Watanabe2, Fuminobu Sato3, Shingo Tamaki3,4, Isao Murata3, Akio Sagara1,2 (1. The Graduate University for Advanced Studies SOKENDAI, 2. National Institute for Fusion Science, 3. Osaka University, 4. Research Fellow of Japan Society for the Promotion of Science)

Keywords:FLiNaK, Molten salt, AmBe neutron source, Tritium production

For investigating the tritium behavior in molten-salt blanket, a new neutron irradiation experiment has started with FLiNaK (LiF-NaF-KF) and AmBe neutron source. Releasing tritium from FLiNaK by running He gas, TF and T2 are recovered separately by water bubbling. The results of recovered tritium measurement using a liquid scintillation counter will be reported.