2023 Annual Meeting
Mar 13 - Mar 15, 2023Tokyo University Komaba Campus
2023 Annual Meeting
Mar 13 - Mar 15, 2023Tokyo University Komaba Campus
[2A02]Study on T production using high-temperature gas-cooled reactor for fusion reactors(1) Evaluation experiment for tritium confinement performance of cylindrical Zr using the test assembly
*Kazunari Katayama Katayama1, Hiroki Isogawa1, Hideaki Matsuura2, Teppei Otsuka3, Minoru Goto4, Shigeaki Nakagawa4, Etsuo Ishitsuka4(1. Kyushu Univ. Eng. Sci., 2. Kyushu Univ. Eng., 3. Kindai Univ., 4. JAEA)
Keywords:
Tritium,HTGR,Zr,Alumina,Permeation
Tritium confinement technology under high temperature conditions is essential for tritium production in high-temperature gas-cooled reactors to start up fusion reactors. In this presentation, we report the results of tritium confinement performance evaluation experiments conducted using a test assembly consisting of an alumina tube and zirconium tubes.