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核融合炉用トリチウムを製造するLi装荷高温ガス炉の核特性評価

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

後藤 実; 奥村 啓介; 中川 繁昭; 松浦 秀明*; 中屋 裕行*; 片山 一成*

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

$$^{6}$$Li(n,$$alpha$$)T反応を用いた高温ガス炉による核融合炉用トリチウム燃料の製造の成立性について検討を行っている。高温ガス炉の核特性解析において実績のあるSRACコードシステムで$$^{6}$$Li(n,$$alpha$$)T反応を取り扱えるように燃焼チェーンを整備し、トリチウム製造高温ガス炉の核特性を評価した。

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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