Out-of-pile tritium release of LiAlO<sub>2</sub> pebble

Xiao Chengjian; Chen Xiaojun; Gong Yu; Huang Hongwen; Ran Guangming; Zhao Linjie; Chen Ping; Zhang Qinying

doi:10.11884/HPLPB201527.016005

Volume 27 Issue 01

Jan. 2015

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Xiao Chengjian, Chen Xiaojun, Gong Yu, et al. Out-of-pile tritium release of LiAlO2 pebble[J]. High Power Laser and Particle Beams, 2015, 27: 016005. doi: 10.11884/HPLPB201527.016005

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Xiao Chengjian, Chen Xiaojun, Gong Yu, et al. Out-of-pile tritium release of LiAlO₂ pebble[J]. High Power Laser and Particle Beams, 2015, 27: 016005. doi: 10.11884/HPLPB201527.016005

Xiao Chengjian, Chen Xiaojun, Gong Yu, et al. Out-of-pile tritium release of LiAlO2 pebble[J]. High Power Laser and Particle Beams, 2015, 27: 016005. doi: 10.11884/HPLPB201527.016005

Citation:

Xiao Chengjian, Chen Xiaojun, Gong Yu, et al. Out-of-pile tritium release of LiAlO₂ pebble[J]. High Power Laser and Particle Beams, 2015, 27: 016005. doi: 10.11884/HPLPB201527.016005

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Out-of-pile tritium release of LiAlO₂ pebble

doi: 10.11884/HPLPB201527.016005

1.
Institute of Nuclear Physics and Chemistry,CAEP,P.O.Box 919-212,Mianyang 621900,China

Received Date: 2014-08-12
Rev Recd Date: 2014-10-08
Publish Date: 2015-01-20

Abstract

Abstract

It is important to understand the tritium properties of tritium breeding materials from the viewpoints of a fusion reactor blanket, the tritium fuel cycle and tritium safety. Out-of-pile tritium release experiments were performed to investigate the effects of heating rate, purge gas composition and platinum catalytic metal on the tritium release behaviors of the lithium aluminate (LiAlO2) ceramic pebbles after neutron-irradiation, and the ESR measuring technique was applied to analyzing the paramagnetic characteristics of irradiation defects. The experimental results show that the bred tritium requires a high temperature region of 750-1000 K to be liberated from LiAlO2 ceramic pebbles corresponding to the slow diffusivity and high desorption activity energy. Catalytic metals and hydrogen in the purge gas can enhance the hydrogen isotope exchange reaction between the tritium on the solid surface and the hydrogen in the purge gas, and accelerate the recovery rate of the molecular tritium (HT). Neutron irradiation can induce F+-center, O--center and O2- center in LiAlO2, and there is a certain relationship between the annihilation behavior of the irradiation defects and the tritium release process.
- LiAlO2,
- tritium breeder,
- tritium release behavior,
- tritium fuel cycle,
- fusion reactor

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