2023 Annual Meeting
Mar 13 - Mar 15, 2023Tokyo University Komaba Campus
2023 Annual Meeting
Mar 13 - Mar 15, 2023Tokyo University Komaba Campus
[2A05]Study on T production using high-temperature gas-cooled reactor for fusion reactors(4) Feasibility study on irradiation test for tritium production capsule
*Etsuo Ishitsuka1, Hai Quan Ho1, Yosuke Shimazaki1, Shigeaki Nakagawa1, Minoru Goto1, Hideaki Matsuura2, Teppei Otsuka3, Kazunari Katayama2, Kazuhiko Iigaki1(1. Japan Atomic Energy Agency, 2. Kyushu University, 3. Kindai University)
Keywords:
Fusion reactor,Production of tritium for initial loading,High-temperature gas-cooled reactor,Irradiation test,Lithium oxide,Hydrogen storage alloy
As part of the development of tritium production using a high-temperature gas-cooled reactor for the initial loading of a fusion reactor, an irradiation test of a tritium production capsule has been studied. In this presentation, a feasibility study on irradiation test using JRR-3 will be introduced.