TY - JOUR
T1 - Study on lithium rod test module and irradiation method for tritium production using high temperature gas-cooled reactor
AU - Koga, Yuki
AU - Matsuura, Hideaki
AU - Ida, Yuma
AU - Okamoto, Ryo
AU - Katayama, Kazunari
AU - Otsuka, Teppei
AU - Goto, Minoru
AU - Nakagawa, Shigeaki
AU - Nagasumi, Satoru
AU - Ishitsuka, Etsuo
AU - Shimazaki, Yosuke
PY - 2018/11
Y1 - 2018/11
N2 - 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.
AB - 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.
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U2 - 10.1016/j.fusengdes.2018.03.029
DO - 10.1016/j.fusengdes.2018.03.029
M3 - Article
AN - SCOPUS:85043515611
VL - 136
SP - 587
EP - 591
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
SN - 0920-3796
ER -