2021 Fall Meeting

Presentation information

Oral presentation

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

[1L07-14] Blanket Material

Wed. Sep 8, 2021 2:45 PM - 5:00 PM Room L

chair: Keisuke Mukai (Kyoto Univ.)

3:30 PM - 3:45 PM

[1L10] Tritium recovery behavior for tritium breeder Li4SiO4–Li2TiO3 mixture material

*Shiori Hirata1, Kyosuke Ashizawa1, Yuki Koyama1, Fei Sun2, Qilai Zhou3, Makoto I Kobayashi4, Yasuhisa Oya1 (1. Grad. Sch., of Shizuoka Univ., 2. Hefei University of Technology, 3. Wuhan University of Technology, 4. NIFS)

Keywords:Mixture ceramics, Tritium behavior, blanket

In the blanket, tritium is produced by neutron reaction with lithium. Li2TiO3 and Li4SiO4 are regarded as the promising candidates for solid breeder materials due to higher lithium density and easy recovery. In this study, Li4SiO4-Li2TiO3 mixture materials with various phase ratios were prepared and their tritium desorption behavior was studied by T (tritium)-TDS.
The neutron irradiation was performed for two kinds of samples with different phase ratios, Li4SiO4-Li2TiO3 and Li4SiO4-2Li2TiO3. Thereafter, the TDS measurement was conducted from R.T. to 1113 K with the heating rates of 5 – 20 K min-1. The activation energy of tritium desorption from Li4SiO4-2Li2TiO3 was evaluated and it was lower than that of Li4SiO4-Li2TiO3. The effect of phase ratio will be discussed in the presentation.