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Current study and future progress for tritium production method using high temperature gas cooled reactor, 2; Study on tritium production and confinement in high-temperature gas-cooled reactor

Katayama, Kazunari*; Matsuura, Hideaki*; Otsuka, Teppei*; Fukada, Satoshi*; Goto, Minoru  ; Nakagawa, Shigeaki  

JAEA and Kyushu University have studied the tritium production method using high temperature gas-cooled reactors (HTGR) for initial fusion reactors. In this method, lithium compounds are loaded into the reactor core and tritium is produced with $$^{6}$$Li(n,a)T reaction. We studied about the optimization of a lithium loading method, an effective tritium containment method and the nuclear thermal design of a lithium loaded HTGR, and consequently we confirmed the feasibility of the tritium production method. This paper describes the results of the hydrogen permeation experiment and the results of the tritium permeation analysis based on the obtained data from the experiments.

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