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.)

4:55 PM - 5:10 PM

[1A15] Comparison of tritium recovery behavior in Li2TiO3-Li4SiO4 ceramic pebbles and powder irradiated with neutron

*Guangfan Tan1, sanfukuji asahi2, hirata shiori2, Qilai Zhou3, Yasuhisa Oya2, Yingchun Zhang1 (1. University of Science and Technology Beijing., 2. Shizuoka Univ., 3. Wuhan University of Technology.)

Keywords:Li2TiO3-Li4SiO4, tritium release, Neutron irradiation, Diffusion coefficient, activation energy

As a superior tritium breeder material, the biphasic Li2TiO3-Li4SiO4 ceramic pebbles have been paid wide attention for its high lithium content, good tritium release performance, low neutron activation behavior, and excellent mechanical property. At present, the tritium release of lithium-based ceramics is mainly studied in powder, which cannot reflect the actual tritium release behavior of ceramic pebbles filled in the blanket. In this paper, the tritium recovery properties in powder and pebble of Li2TiO3-Li4SiO4 biphasic ceramic irradiated with neutron were investigated, respectively. Therefore, this experimental result will provide new theoretical guidance for the tritium release behavior of breeder material in the future.