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Study on lithium rod test module and irradiation method for tritium production using high temperature gas-cooled reactor

Authors :
Satoru Nagasumi
Ryo Okamoto
Etsuo Ishitsuka
Kazunari Katayama
Yosuke Shimazaki
Teppei Otsuka
Yuma Ida
Shigeaki Nakagawa
Yuki Koga
Minoru Goto
Hideaki Matsuura
Source :
Fusion Engineering and Design. 136:587-591
Publication Year :
2018
Publisher :
Elsevier BV, 2018.

Abstract

Large quantities of tritium are required to start up fusion reactors and conducts engineering tests using tritium for a fusion blanket system. However, tritium is very rare and kg orders of tritium must be produced artificially. Tritium production, by 6Li(n,α)T reaction using a high temperature gas-cooled reactor (HTGR) has been proposed. This method considers the loading of Li rods into burnable poison holes in the HTGR. In this paper, the Li rod suited for use in the High Temperature engineering Test Reactor (HTTR) was designed, and tritium production and leakage from Li-rod capsules were evaluated by adjusting the thicknesses of LiAlO2, alumina, and Zr layers. An irradiation test scenario to be conducted in the HTTR for demonstration of the Li rod’s tritium production and containment performance was presented.

Details

ISSN :
09203796
Volume :
136
Database :
OpenAIRE
Journal :
Fusion Engineering and Design
Accession number :
edsair.doi...........165df413ed6712e009535e2f2ef76b75