[1G11-14] Production, Separation, Recovery

[1G11] Study on T production method using high-temperature gas-cooled reactor for fusion reactors

Hydrogen absorption property of Ni-coated Zr sphere

*Hideaki Matsuura¹, Hiromi Kawai¹, Kanta Kitagawa¹, Aoi Furuya¹, Kazunari Katayama¹, Teppei Otsuka², Shigeaki Nakagawa³, Etsuo Ishitsuka³, Kenji Tobita⁴, Youji Someya⁵ (1. Kyushu Univ., 2. Kindai Univ., 3. JAEA, 4. Tohoku Univ., 5. QST)

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

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 have investigated 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. This time, we report on the absorption property of hydrogen by the Zr sphere when coexisting with oxides (LiAlO₂ and Al₂O₃) for longer periods, i.e., more than a week, in a similar circumstance to that of the HTGR.