2020 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-3 Tritium Science and Technology (Fuel Recovery and Refining, Measurement, Iisotope Effect, Safe Handling)

[2L01-08] Tritium Release Behaviors, Production, Measurement

Tue. Mar 17, 2020 10:00 AM - 12:10 PM Room L (Lecture Bildg. S 2F S-22)

Chair:Teppei Otsuka(Kindai Univ.)

11:15 AM - 11:30 AM

[2L06] T-containment performance of Li rod in high-temperature gas-cooled reactor for T production

(3)Eveluation of T flowout from Li rods

*Hideaki Matsuura1, Yuki Koga1, Takuro Suganuma1, Kazunari Katayama2, Teppei Otsuka3, Minoru Goto4, Shigeaki Nakagawa4, Etsuo Ishitsuka4, Shinpei Hamamoto4, Kenji Tobita5 (1. Kyushu Univ., 2. Dept. Eng. and Sci, Kyushu Univ., 3. Kindai Univ., 4. JAEA, 5. QST)

Keywords:Tritium, Li rod, Zirconium, Alumina, Nickel coating, High-temperature gas-cooled reactor

For prior technical tests of tritium circulation and blanket systems of a demonstration fusion reactor and for the startup operation, it is necessary to provide a sufficient amount of tritium from an outside source. We proposed the tritium production using the high-temperature gas-cooled reactor (HTGR). We have considered tritium-containment using a Li rod with Zr inside and covered by Al2O3 layer. In the rod, reduction in tritium absorption performance of Zr due to oxidization via interacting with coexisting oxides was one of the matter to be resolved. Recently, one of the collaborators experimentally clarified the degree of the reduction in the tritium absorption performance of Zr by Ni coating in high-temperature environment. In this presentation, on the basis of the new data, the amounts of tritium flow out from the Li rod for typical HTGRs are estimated. It is shown most amount of tritium can be contained in the Li rods.