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.)

11:00 AM - 11:15 AM

[2L05] T-containment performance of Li rod in high-temperature gas-cooled reactor for T production

(2)Evaluation of tritium confinement performance by the assembly simulating Li rod

*Kazunari Katayama1, Daisuke Henzan1, Hideaki Matsuura2, Teppei Otsuka3, Minoru Goto4, Shigeaki Nakagawa4, Etsuo Ishitsuka4, Shinpei Hamamoto4, Kenji Tobita5 (1. Dept. Eng. and Sci., Kyushu Univ., 2. Kyushu Univ., 3. Kindai Univ., 4. JAEA, 5. QST)

Keywords:Tritium, Zirconium, Alumina, HTGR

Tritium production using the high-temperature gas-cooled reactor has been discussed for start-up of a fusion reactor. One of the challenges is the development of confinement technology for tritium produced by the nuclear reaction between lithium (Li) and neutrons. Based on previous studies, the Li rod structure in which a Li compound is sandwiched between zirconium (Zr) having high hydrogen storage performance and the whole is covered with alumina (Al2O3) has been proposed. In this study, the assembly simulating Li rod consisting of one-side sealed Zr pipe and one-side sealed Al2O3 pipe was prepared, and a tritium-containing gas was supplied under a high temperature of 700 ° C to evaluate the confinement performance of the proposed structure.