The Influence of hydrogen absorption performance of Zr on tritium confinement properties of Li rod in HTGR

Okamoto, Ryo*; Matsuura, Hideaki*; Ida, Yuma*; Koga, Yuki*; Katayama, Kazunari*; Otsuka, Teppei*; Goto, Minoru ; Nakagawa, Shigeaki ; Ishitsuka, Etsuo ; Nagasumi, Satoru

A study on tritium production using a high-temperature gas-cooled reactor has been carried out and it was proposed that zirconium is loaded into the lithium irradiation capsule to confine tritium within the irradiation capsule under high temperature condition. In this study, zirconium loading method was examined by numerical calculations to improve the tritium confinement. As a result, it was found that improvement in the tritium confinement can be expected by loading spherical zirconium into the irradiation capsule.

Language	:	Japanese
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Meeting title	:	日本原子力学会2018年春の年会
Held date	:	2018/03
Location (city)	:	吹田
Location (country)	:	日本
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DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	高温ガス炉; トリチウム; ジルコニウム; 吸蔵
Research Facility	:	HTTR(高温工学試験研究炉)
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Cooperating Institute	:	近畿大学; 九州大学

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Registration No. : BB20171856
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