2023年春の年会

講演情報

一般セッション

VI. 核融合工学 » 601-2 核融合炉材料工学(炉材料,ブランケット,照射挙動)

[1A12-15] 中性子増倍材/固体増殖材

2023年3月13日(月) 16:10 〜 17:15 A会場 (11号館1F 1101)

座長:徐 ぎゅう(京大)

16:55 〜 17:10

[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.)

キーワード: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.