2023 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[1A12-15] Neutron Multiplier and Solid Breeder Materials

Mon. Mar 13, 2023 4:10 PM - 5:15 PM Room A (11 Bildg.1F 1101)

Chair:Qiu Xu(Kyoto Univ.)

4:25 PM - 4:40 PM

[1A13] Changes in Tritium Release Behavior of Li2TiO3-Li4SiO4 Mixed Ceramic Materials by Lead Addition Rate

*Asahi Sanfukuji1, Qilai Zhou2, Tan Guangfan3, Makoto Koayashi4, Yasuhisa Oya1 (1. Shizuoka Univ., 2. Wuhan University of Technology, 3. University of Science and Technology Beijing, 4. NIFS)

Keywords:Blanket, Tritium behavior, Mixture ceramics

It is necessary to generate tritium in a fusion reactor. Elucidation of the tritium release behavior of solid blankets, which are tritium growth materials, is essential for tritium recovery. In this study, Li2TiO3-Li4SiO4 with lead addition samples prepared at Wuhan University of Technology was irradiated with neutrons at the Kyoto University Research Reactor (KUR), and tritium release behavior was evaluated by temperature desorption (TDS) and liquid scintillation (LSC), and defective species were identified and their extinction behavior was evaluated by electron spin resonance (ESR). In the presentation, we will present how the tritium release behavior changed due to the change in the amount of lead added.