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Report No.

Evaluation of nuclear characteristics of lithium loaded HTGR for tritium production for fusion reactors

Goto, Minoru  ; Okumura, Keisuke ; Nakagawa, Shigeaki  ; Matsuura, Hideaki*; Nakaya, Hiroyuki*; Katayama, Kazunari*

A feasibility study of a High Temperature Gas-cooled Reactor (HTGR) for tritium production using $$^{6}$$Li(n,$$alpha$$)T reaction for fusion reactors has been conducted. In this study, the burn-up chain was modified to treat $$^{6}$$Li(n,a)T reaction directory in neutronics calculations, and then the feasibility study was performed from the view point of nuclear characteristics using SRAC code system, which has experience in neutronics analysis of HTGRs.



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