Release behavior of hydrogen isotopes in deuterium-irradiated Li2TiO3
Release time:2024-06-03
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DOI number:10.1016/j.fusengdes.2016.05.022
Affiliation of Author(s):材料科学与工程学院
Journal:Fusion Engineering and Design
Key Words:Tritium breeding materials, Behavior of release and retention, Irradiation defects, Li2TiO3ceramic
Abstract:The release mechanism of tritium in breeding materials is one of the critical issues in fusion reactor. Inthis study, thermal desorption spectroscopy (TDS) experiments were performed at heating rates of 5, 10,and 15 K/min to elucidate the release kinetics of deuterium from trapping sites. The deuterium spectra forLi2TiO3irradiated by deuterium ions in different heating rates featured an obvious peak at temperatureranging from 550 K to 800 K. The activation energy of deuterium release from Li2TiO3is 0.53 eV. X-raydiffraction (XRD) results indicate that Li2TiO3crystals are damaged by D+irradiation, but no new phasesare produced. After TDS experiments, the crystallinity of Li2TiO3crystals recovers as that of unirradiatedsamples. Li2TiO3samples become dark blue after annealing in vacuum and become white again afterannealing in air. According to X-ray Photoelectron Spectroscopy (XPS), the surface compounds of coloredLi2TiO3have changed. This may be attributed to the formation of oxygen defect in reduction atmosphere.
Co-author:Yuping Xu, Feng Liu, Zhongqing An, Tao Lu, Maoqiao Xiang,Haishan Zhou, Xiaochun Li, Mingzhong Zhao, Yingchun Zhang, Guang-nan Luoa
First Author:Jing Wang
Indexed by:Journal paper
Correspondence Author:Qiang Qi
Discipline:工科
Issue:113
Page Number:318–323
ISSN No.:0920-3796
Translation or Not:no
Date of Publication:2016-05-25
Pre One:Wang, Jing; Hatano, Yuji*; Hinoki, Tatsuya; Alimov, Vladimir Kh.; Spitsyn, Alexander V.; Bobyr, Nikolay P.; Kondo, Sosuke; Toyama, Takeshi; Lee, Heun Tae; Ueda, Yoshio; Schwarz-Selinger, Thomas; Deuterium retention in W and binary W alloys irradiated with high energy Fe ions, Journal of Nuclear Materials, 2021, 545(1): 0-152749.