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Comparison of tritium release behavior in Li2TiO3 and promising core-shell Li2TiO3-Li4SiO4 biphasic ceramic pebbles

文献类型：期刊论文

作者Qi, Qiang1; Wang, Jing1; Zhou, Qilai2; Zhang, Yingchun3; Zhao, Mingzhong2; Gu, Shouxi1; Nakata, Moeko2; Zhou, Haishan1; Oya, Yasuhisa2; Luo, Guang-Nan1
刊名JOURNAL OF NUCLEAR MATERIALS
出版日期2020-10-01
卷号539
ISSN号0022-3115
关键词Nuclear fusion Tritium release Neutron irradiation Diffusion coefficient
DOI10.1016/j.jnucmat.2020.152330
通讯作者Luo, Guang-Nan(gnluo@ipp.ac.cn)
英文摘要In a D-T fusion reactor, self-sufficiency of tritium is one of the critical issues to maintain steady-state operation of the reactor. Li2TiO3 and core-shell Li2TiO3-Li4SiO4 biphasic pebbles have been irradiated by thermal neutrons in Kyoto University. T-TDS (Tritium-Thermal Desorption Spectroscopy) was performed in Shizuoka University. There is one main tritium trapping site in neutron irradiated Li2TiO3. However, three tritium trapping sites are introduced in neutron irradiated core-shell Li2TiO3- Li4SiO4. The two peaks at lower temperature agree with that of Li2TiO3 which can be attributed to tritium release from Li2TiO3 including shell and core. The peak at higher temperature is mainly considered as tritium release from Li4SiO4. The amount of tritium released from core-shell Li2TiO3-Li4SiO4 is slight higher than that of Li2TiO3. The kinetic parameters of tritium diffusion in Li2TiO3 have been obtained. In the case of Li2TiO3 and core-shell Li2TiO3-Li4SiO4, almost all the tritium is released as HTO observed from T-TDS. Purge gas has little effect on tritium release, indicating tritium release from Li2TiO3 was mainly controlled by tritium diffusion in Li2TiO3 grain. (C) 2020 Elsevier B.V. All rights reserved.
WOS关键词LITHIUM TITANATE ; BREEDER ; TEMPERATURE ; ITER
资助项目National MCF Energy RD Program[2018YFE0307103] ; National Natural Science Foundation of China[11605230] ; National Natural Science Foundation of China[51372017]
WOS研究方向Materials Science ; Nuclear Science & Technology
语种英语
出版者ELSEVIER
WOS记录号WOS:000564000600011
资助机构National MCF Energy RD Program ; National Natural Science Foundation of China
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/70494]  
专题中国科学院合肥物质科学研究院
通讯作者Luo, Guang-Nan
作者单位1.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
2.Shizuoka Univ, Suruga Ku, 836 Ohya, Shizuoka 4228529, Japan
3.Univ Sci & Technol Beijing, Beijing 100083, Peoples R China
推荐引用方式
GB/T 7714		 Qi, Qiang,Wang, Jing,Zhou, Qilai,et al. Comparison of tritium release behavior in Li2TiO3 and promising core-shell Li2TiO3-Li4SiO4 biphasic ceramic pebbles[J]. JOURNAL OF NUCLEAR MATERIALS,2020,539.
APA Qi, Qiang.,Wang, Jing.,Zhou, Qilai.,Zhang, Yingchun.,Zhao, Mingzhong.,...&Luo, Guang-Nan.(2020).Comparison of tritium release behavior in Li2TiO3 and promising core-shell Li2TiO3-Li4SiO4 biphasic ceramic pebbles.JOURNAL OF NUCLEAR MATERIALS,539.
MLA Qi, Qiang,et al."Comparison of tritium release behavior in Li2TiO3 and promising core-shell Li2TiO3-Li4SiO4 biphasic ceramic pebbles".JOURNAL OF NUCLEAR MATERIALS 539(2020).

入库方式： OAI收割

来源：合肥物质科学研究院

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