Oct 6 – 8, 2025
Kyoto University Uji campus
Asia/Tokyo timezone

Study on tritium release behavior of ceramic pebbles fabricated by Centrifugal granulation method

Not scheduled
20m
Kihada Hall (Obaku Plaza) (Kyoto University Uji campus)

Kihada Hall (Obaku Plaza)

Kyoto University Uji campus

Kyoto University Uji campus, Gokasho, Uji, Kyoto, 611-0011, Japan

Speaker

guangfan tan

Description

guangfan tan, Yasuhisa Oya, Qilai Zhou

One of the key problems in fusion reactor fuel cycle is the efficient acquisition of tritium. How to obtain ceramic pebbles with high lithium content, excellent mechanical properties and good tritium release is the future development goal. In this study, Li2TiO3, Li4SiO4 and biphasic Li2TiO3-Li4SiO4 pebbles were successfully prepared by centrifugal granulation. The behavior and mechanism of tritium release under neutron irradiation were systematically studied. Firstly, by optimizing the granulation process and sintering conditions, the pebbles with uniform particle size distribution, high density and excellent mechanical properties were prepared to ensure their structural stability and application potential in the nuclear environment. Then, the tritium release characteristics of different materials at different radiation doses and temperatures were investigated by neutron irradiation experiments. The solution, diffusion and release mechanism of tritium in pebbles were analyzed by thermal desorption spectroscopy (TDS). At the same time, electron paramagnetic resonance (EPR) technique was used to study the defect type, concentration change and annihilation process of irradiated microspheres in detail, in order to reveal the influence of irradiated defects on the retention and release of tritium. The results of this study not only deepened the understanding of the tritium release mechanism of Li2TiO3, Li4SiO4 and their composites under irradiation, but also provided an important theoretical and experimental basis for optimizing the microstructure of the tritium breeding materials, improving the efficiency of tritium release and reducing the risk of tritium retention. This study is of great significance for the development and optimization of tritium breeding materials in future fusion reactor.

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