Li nuclear heat generation in the HTGR for T production and effect on T containment performance

Koga, Yuki*; Matsuura, Hideaki*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru ; Hamamoto, Shimpei ; Ishitsuka, Etsuo ; Nakagawa, Shigeaki ; Tobita, Kenji*

The tritium confinement performance of the designed irradiation capsule was evaluated for the case where tritium was produced by loading Li compound into GTHTR300. Calculation of tritium outflow from the irradiation capsule was performed taking into account the nuclear heat generation of the $^{6}$ Li(n,)T reaction in addition to the core temperature. As a result, by taking into account nuclear heat, the outflow of T was reduced by 15% from the previous calculation results, and the confinement performance was improved.

Language	:	Japanese
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Meeting title	:	第36回プラズマ・核融合学会年会
Held date	:	2019/11
Location (city)	:	春日井
Location (country)	:	日本
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Keywords	:	高温ガス炉; 核融合; トリチウム; 閉じ込め
Research Facility	:	HTTR(高温工学試験研究炉)
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Article of JAEA R&D Review	:
Cooperating Institute	:	近畿大学; 九州大学; 量子科学技術研究開発機構

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Registration No. : BB20191524
JAEA Abstracts No. :
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