Release behavior of hydrogen isotopes in deuterium-irradiated Li2TiO3
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DOI码：10.1016/j.fusengdes.2016.05.022
所属单位：材料科学与工程学院
发表刊物：Fusion Engineering and Design
关键字：Tritium breeding materials, Behavior of release and retention, Irradiation defects, Li2TiO3ceramic
摘要：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.
合写作者：Yuping Xu, Feng Liu, Zhongqing An, Tao Lu, Maoqiao Xiang,Haishan Zhou, Xiaochun Li, Mingzhong Zhao, Yingchun Zhang, Guang-nan Luoa
第一作者：Jing Wang
论文类型：期刊论文
通讯作者：Qiang Qi
学科门类：工科
期号：113
页面范围：318–323
ISSN号：0920-3796
是否译文：否
发表时间：2016-05-25