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

doi:10.1016/j.jnucmat.2020.152330

	Comparison of tritium release behavior in Li2TiO3 and promising core-shell Li2TiO3-Li4SiO4 biphasic ceramic pebbles
	Qi, Qiang 3; Wang, Jing 3; Zhou, Qilai 2; Zhang, Yingchun 1; Zhao, Mingzhong 2; Gu, Shouxi 3; Nakata, Moeko 2; Zhou, Haishan 3; Oya, Yasuhisa 2; Luo, Guang-Nan 3
刊名	JOURNAL OF NUCLEAR MATERIALS
	2020-10-01
卷号	539
关键词	Nuclear fusion Tritium release Neutron irradiation Diffusion coefficient
ISSN号	0022-3115
DOI	10.1016/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.
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关键词	LITHIUM TITANATE ; BREEDER ; TEMPERATURE ; ITER
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
内容类型	期刊论文
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.Univ Sci & Technol Beijing, Beijing 100083, Peoples R China 2.Shizuoka Univ, Suruga Ku, 836 Ohya, Shizuoka 4228529, Japan 3.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, 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).