Influence of radiation defects on deuterium permeation behavior in tungsten
文献类型:期刊论文
| 作者 | Liu, Feng1,2,3 ; Zhou, Hai-Shan2 ; Xu, Chuan4; Cao, Xingzhong5; Ding, Fang2 ; Luo, Guang-Nan2
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| 刊名 | JOURNAL OF NUCLEAR MATERIALS
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| 出版日期 | 2020-12-15 |
| 卷号 | 542 |
| 关键词 | Hydrogen isotopes Tungsten Radiation defects Permeation Diffusion |
| ISSN号 | 0022-3115 |
| DOI | 10.1016/j.jnucmat.2020.152455 |
| 通讯作者 | Liu, Feng(liufeng@njust.edu.cn) |
| 英文摘要 | Understanding the hydrogen isotope (H) permeation behavior in neutron irradiated tungsten (W) is highly desired for the accurate prediction of H behavior in W first walls in a fusion DEMO reactor. Contrary studies have been published where some indicated a relatively higher H permeability in the irradiated W whereas others showed a lower H permeability. In these studies the radiation defects were produced with ions (as surrogates for neutrons) and were concentrated in a shallow layer (<200 nm), their effects could be mixed up with surface effects during H permeation. Herein W specimens damaged to 800 nm by Au-ion implantation are adopted to investigate the effects of radiation defects on deuterium (D) permeation. Microstructural analyses with slow positron annihilation technique and transmission electron microscopy revealed that vacancy-type defects and dislocation loops were produced in the implanted W. Results from D-2 gas-driven permeation measurements at 700-10 00 K showed, surprisingly, radiation defects did not influence the D permeability. The phenomenon was illustrated from a thermodynamic perspective. Radiation-induced dislocations and/or monovacancies, possessing low H coverage fractions, do not affect permeability because their effects on effective diffusivity and solubility can fully cancel each other. Vacancy clusters, having a high fractional H coverage and owing to their strong trapping nature, will not come to effect during the steady-state permeation portion, thus do not contribute to permeability. (C) 2020 Elsevier B.V. All rights reserved. |
| WOS关键词 | GAS-DRIVEN PERMEATION ; HYDROGEN ISOTOPES ; W-ALLOYS ; PERMEABILITY ; TEMPERATURE ; DIFFUSIVITY ; IRRADIATION ; SOLUBILITY ; RETENTION ; STEELS |
| 资助项目 | National Natural Science Foundation of China[11705232] ; National Magnetic Confinement Fusion Science Program of China[2015GB109001] ; Open fund of Key Laboratory of Materials Preparation and Protection for Harsh Environment (Nanjing Univ. of Aeronautics and Astronautics), Ministry of Industry and Information Technology[56XCA18159] |
| WOS研究方向 | Materials Science ; Nuclear Science & Technology |
| 语种 | 英语 |
| WOS记录号 | WOS:000583242500016 |
| 出版者 | ELSEVIER |
| 资助机构 | National Natural Science Foundation of China ; National Magnetic Confinement Fusion Science Program of China ; Open fund of Key Laboratory of Materials Preparation and Protection for Harsh Environment (Nanjing Univ. of Aeronautics and Astronautics), Ministry of Industry and Information Technology |
| 源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/105142] ![]() |
| 专题 | 中国科学院合肥物质科学研究院 |
| 通讯作者 | Liu, Feng |
| 作者单位 | 1.Nanjing Univ Sci & Technol, Sch Sci, Nanjing 210094, Peoples R China 2.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China 3.Nanjing Univ Aeronaut & Astronaut, Key Lab Mat Preparat & Protect Harsh Environm, Minist Ind & Informat Technol, Nanjing 210094, Peoples R China 4.Peking Univ, Inst Heavy Ion Phys, State Key Lab Nucl Phys & Technol, Beijing 100871, Peoples R China 5.Chinese Acad Sci, Inst High Energy Phys, Beijing 100049, Peoples R China |
| 推荐引用方式 GB/T 7714 | Liu, Feng,Zhou, Hai-Shan,Xu, Chuan,et al. Influence of radiation defects on deuterium permeation behavior in tungsten[J]. JOURNAL OF NUCLEAR MATERIALS,2020,542. |
| APA | Liu, Feng,Zhou, Hai-Shan,Xu, Chuan,Cao, Xingzhong,Ding, Fang,&Luo, Guang-Nan.(2020).Influence of radiation defects on deuterium permeation behavior in tungsten.JOURNAL OF NUCLEAR MATERIALS,542. |
| MLA | Liu, Feng,et al."Influence of radiation defects on deuterium permeation behavior in tungsten".JOURNAL OF NUCLEAR MATERIALS 542(2020). |
入库方式: OAI收割
来源:合肥物质科学研究院
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