[2A01-05] Tritium Production

[2A04] Study on T production using high-temperature gas-cooled reactor for fusion reactors

(3) Hydrogen-absorption performance of Ni-coated Zr spheres and preparation of the irradiation test module

*Hideaki Matsuura¹, Taisei Abe¹, Kanta Kitagawa¹, Hiromi Kawai¹, Kazunari Katayama², Teppei Otsuka³, Minoru Goto⁴, Shigeaki Nakagawa⁴, Etsuo Ishitsuka⁴, Shinpei Hamamoto⁵ (1. Kyushu Univ., 2. Kyushu Univ. Eng. Sci, 3. KINDAI Univ., 4. Kyushu University, 5. Blossom Energy)

Keywords:Tritium, High-temperature gas-cooled reactor, Ni-coated Zr shpere, Li-loading test module, Fusion DEMO reactor

Tritium (T) preparation is necessary for initial fusion reactor startup operation. We have proposed the T production using a high-temperature gas-cooled reactor (HTGR). At this stage, we aim to assess the compatibility of electricity and T production; hence, how to stably contain T in a Li-loading rod is a crucial issue. We investigate the Li-loading rod structure using dense-quality Al₂O₃ and Zr spheres with Ni coating and experimentally measured the basic hydrogen absorption properties of a Zr sphere with Ni coating in a circumstance like that with the HTGR. A test module prototype is produced for initial irradiation test. The current typical specification of the test module is reported.