Current study and future progress for tritium production method using high temperature gas cooled reactor, 3; Nuclear and thermal design of the high temperature gas-cooled reactor for tritium production and power generation

Goto, Minoru  ; Nakagawa, Shigeaki  ; Matsuura, Hideaki*; Katayama, Kazunari*

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 Li(n,)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 feasibility of the nuclear thermal design of the lithium loaded HTGR tritium production.