Study on T production using high-temperature gas-cooled reactor for fusion reactors, 4; Feasibility study on irradiation test for tritium production capsule

Ishitsuka, Etsuo ; Ho, H. Q. ; Shimazaki, Yosuke ; Nakagawa, Shigeaki ; Goto, Minoru ; Matsuura, Hideaki*; Otsuka, Teppei*; Katayama, Kazunari*; Iigaki, Kazuhiko

As part of the development of tritium production using a high-temperature gas-cooled reactor for the initial loading of a fusion reactor, an irradiation test of a tritium production capsule has been studied. In this presentation, a feasibility study on irradiation test using JRR-3 will be introduced.

Language	:	Japanese
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Meeting title	:	日本原子力学会2023年春の年会
Held date	:	2023/03
Location (city)	:	東京
Location (country)	:	日本
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Keywords	:	高温ガス炉; 核融合炉; 初装荷用トリチウム製造; 照射試験; リチウム酸化物; 素吸蔵合金
Research Facility	:	HTTR(高温工学試験研究炉)
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Registration No. : BB20221408
JAEA Abstracts No. :
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