Work

Experimental investigation of tritium release from LiAlO2 and absorption into Zr

Year: 2025

Type: article

Abstract: Tritium (T) production using a high-temperature gas-cooled reactor (HTGR) has been proposed to arrange initial T inventory for nuclear fusion reactors. For the establishment of this method, the behavior of T in a Li-loading rod (Li-rod), which contains LiAlO2 and zirconium (Zr), needs to be understood. In this study, a powdered LiAlO2 sample was heated in H2 containing Ar gas flow to observe water formation reaction. Then, a powdered Zr sample was heated in humid Ar gas flow to investigate the temperature dependence of H2O reduction rate on the Zr. Finally, the neutron-irradiated LiAlO2 mixed with Zr, which was preheated at 700 °C in a sealed quartz tube, was heated in Ar gas flow, and the release behavior of gaseous T (HT, T2) and tritiated water vapor (HTO, T2O) was observed. Based on the results, it is suggested that LiAlO2 should be in advance heated in reduction atmosphere to remove adsorbed water and unstable oxygen to suppress the release of T in chemical form of HTO, and Li-rod should be operated at higher temperatures over 700 ºC to decrease the mass transfer resistance by an oxide layer on Zr.

Source: Fusion Engineering and Design

DOI: 10.1016/j.fusengdes.2025.115471

Authors: Seiyo Kobayashi, Kazunari Katayama, Hiroki Isogawa, Hideaki Matsuura, Kenta Akashi, Yuto Iinuma

Institutions: Kyushu University, Kyoto University, Institute for Integrated Radiation and Nuclear Science, Kyoto University

Language: English

Topic: Fusion materials and technologies

Subfield: Materials Chemistry

Field: Materials Science

Domain: Physical Sciences

SDG: Affordable and clean energy

Open Access status: hybrid

Estimated APC paid: $2,810