Li-rod structure in high-temperature gas-cooled reactor as a tritium production device for fusion reactors

被引：7

作者：

Matsuura, Hideaki ^{[1
]}

Okamoto, Ryo ^{[1
]}

Koga, Yuki ^{[1
]}

Suganuma, Takuro ^{[1
]}

Katayama, Kazunari ^{[2
]}

Otsuka, Teppei ^{[3
]}

Goto, Minoru ^{[4
]}

Nakagawa, Shigeaki ^{[4
]}

Ishitsuka, Etsuo ^{[4
]}

Tobita, Kenji ^{[5
]}

机构：

[1] Kyushu Univ, Dept Appl Quantum Phys Nucl Engn, 744 Motooka, Fukuoka, Fukuoka 8190395, Japan

[2] Kyushu Univ, Dept Adv Energy Eng Sci, 6-1 Kasugakouen, Kasuga, Fukuoka 8160811, Japan

[3] Kindai Univ, Dept Elect & Elect Engn, 3-4-1 Kowakae, Higashiosaka, Osaka 5770818, Japan

[4] Japan Atom Energy Agcy, 4002 Narita Cho, Oarai, Ibaraki 3111393, Japan

[5] Natl Inst Quantum & Radiol Sci Tech, Rokkasho, Aomori 0393212, Japan

来源：

FUSION ENGINEERING AND DESIGN | 2019年 / 146卷

关键词：

Tritium; Lithium; Zirconium; Lithium-loading rod; High-temperature gas-cooled reactor; HTTR;

D O I：

10.1016/j.fusengdes.2019.02.009

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Production of tritium using a high-temperature gas-cooled reactor (HTGR) has been studied for a prior engineering test with tritium handling and for the startup operation of a demonstration fusion reactor. For this purpose, the hydrogen absorption speed of Zr in a Li-loading rod for the reactor operation is experimentally measured, and an analysis model is presented to evaluate the tritium outflow from the Li rod in a high-temperature engineering test reactor (HTTR). On the basis of the presented model, the structure of the Li-loading rod for the demonstration test using the HTTR is proposed.

引用

页码：1077 / 1081

页数：5

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