高温ガス炉を用いたトリチウム製造の検討; 照射試験用試験体の構造及び実験法

Study on tritium production using high-temperature gas-cooled reactor for fusion reactors; Structure of the irradiation test module and experimental method

北川 堪大*; 松浦 秀明*; 川井 大海*; 片山 一成*; 大塚 哲平*; 石塚 悦男   ; 中川 繁昭  ; 後藤 実*; 飛田 健次*; 小西 哲之*; 染谷 洋二*; 坂本 宜照*

Kitagawa, Kanta*; Matsuura, Hideaki*; Kawai, Hitomi*; Katayama, Kazunari*; Otsuka, Teppei*; Ishitsuka, Etsuo; Nakagawa, Shigeaki; Goto, Minoru*; Tobita, Kenji*; Konishi, Satoshi*; Someya, Yoji*; Sakamoto, Yoshiteru*

高温ガス炉における核融合炉用T(トリチウム)製造を検討している。常温から高温まで温度変化させた場合のNi被覆Zr球の水素吸収性能を観測し解析モデルを確認・検討した上で、照射試験のための試験体構造(Ni被覆Zr球数やLiAlO量)や実験法について検討した。

Tritium production using a high temperature gas cooled reactor has been studied to get for the start-up of an initial DEMO fusion reactor and for technical testing of related tritium circulation systems. The characteristics of hydrogen absorption in the case of change from room temperature to high temperature for zirconium particle with nickel coating was obtained and investigated the analytical simulation model. And the configuration (for example, the numbers of zirconium particle with nickel coating and the amount of LiAlO) of test specimen for irradiation test and the test method were discussed.