2023 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)

[2A01-05] Tritium Production

Tue. Mar 14, 2023 10:30 AM - 11:55 AM Room A (11 Bildg.1F 1101)

Chair:Makoto Inami Kobayashi(NIFS)

11:30 AM - 11:45 AM

[2A05] Study on T production using high-temperature gas-cooled reactor for fusion reactors

(4) Feasibility study on irradiation test for tritium production capsule

*Etsuo Ishitsuka1, Hai Quan Ho1, Yosuke Shimazaki1, Shigeaki Nakagawa1, Minoru Goto1, Hideaki Matsuura2, Teppei Otsuka3, Kazunari Katayama2, Kazuhiko Iigaki1 (1. Japan Atomic Energy Agency, 2. Kyushu University, 3. Kindai University)

Keywords:Fusion reactor, Production of tritium for initial loading, High-temperature gas-cooled reactor, Irradiation test, Lithium oxide, Hydrogen storage alloy

As part of the development of tritium production using a high-temperature gas-cooled reactor for the initial loading of a fusion reactor, an irradiation test of a tritium production capsule has been studied. In this presentation, a feasibility study on irradiation test using JRR-3 will be introduced.