2023 Fall Meeting

Presentation information

Oral presentation

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

[2L04-07] Tritium Breeding Materials/Neutron-Multiplier Materials

Thu. Sep 7, 2023 10:50 AM - 12:00 PM Room L (ES Bildg. 3F ES033)

Chair:Teruya Tanaka(NIFS)

10:50 AM - 11:05 AM

[2L04] Preparation of Li2TiO3-0.5Li4SiO4-Pb lithium ceramic and its hydrogen isotope release behavior

*Qilai Zhou1,2, Asahi Sanfukuji1, Yasuhisa Oya1 (1. Shizuoka Univ., 2. Wuhan Univ. of Technol.)

Keywords:Tritium breeder, Tritium, Deterium, Lithium ceramic, Neutron irradiation

Li2TiO3-0.5Li4SiO4-Pb was prepared by the addition of lead (Pb) into lithium ceramic as tritium breeder candidate for fusion reactors. The ceramics with and without Pb were irradiated by neutrons in KUR. The tritium release behavior was compared using the tritium thermal desorption spectroscopy system (T-TDS). It was found that the tritium release rate at the low temperature side was increased by Pb addition. For the tritiated water (HTO), 80 % can be released when the isothermal heating temperature was 683 K. For the HT, almost 100 % can be released when the heating temperature was 814 K. 3 keV D2+ irradiation and subsequent TDS measurements showed that D2 desorption of Li2TiO3-0.5Li4SiO4-Pb was higher and HDO water desorption was lower.

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