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.)

4:40 PM - 4:55 PM

[1A14] Effect of irradiation dose on tritium release behavior of neutron irradiated Li2TiO3-Li4SiO4 mixed ceramic

*Qilai Zhou1,2, Asahi Sanfukuji1, Tan Guangfan1,3, Oya Yasuhisa1 (1. Shizuoka Univ., 2. Wuhan Univ. of Technol., 3. The Univ. of Sci. and Technol. Beijing)

Keywords:Tritium breeder, Nuclear fusion, Neutron irradiation, Hydrogen isotope, Lithium ceramic

Li2TiO3-Li4SiO4 is considered as the candidate tritium breeding material. In this study, neutron irradiation with different flux and fluence was performed. The tritium release behavior was investigated by thermal desorption spectroscopy (TDS) and isothermal heating experiment. It was found that the TDS spectra shifted to low-temperature side at high neutron fluence. With the decrease in neutron flux, the shape of TDS spectra became wider and the release peaks increased. Besides, the simulated TDS spectra based on the diffusion model and trapping / de-trapping process can reflect the isothermal heating experiment results. Further, there was another tritium release peak after the finish of isothermal heating, which indicated that tritium remained inside the ceramic. Therefore, both the diffusion and trapping / detrapping processes should be considered.