Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation
文献类型：期刊论文
| 作者 | Ding, Xiao-Yu2,3; Xu, Qiu1; Zhu, Xiao-yong4,5,6; Luo, Lai-Ma4,5,6; Huang, Jian-Jun3; Yu, Bin3; Gao, Xiang7 ; Li, Jian-Gang7; Wu, Yu-Cheng4,5,6
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| 刊名 | NUCLEAR ENGINEERING AND TECHNOLOGY
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| 出版日期 | 2020-12-01 |
| 卷号 | 52 |
| ISSN号 | 1738-5733 |
| 关键词 | Oxide dispersion-strengthened Pre-irradiation Microstructure evolution He+ ions Deuterium retention |
| DOI | 10.1016/j.net.2020.05.022 |
| 通讯作者 | Ding, Xiao-Yu(dingxiaoyu0903@126.com) ; Wu, Yu-Cheng(ycwu@hfut.edu.cn) |
| 英文摘要 | Oxide dispersion-strengthened materials W-1wt%Pr2O3 and W-1wt%La2O3 were synthesized by wet chemical method and spark plasma sintering. The field emission scanning electron microscopy (FE-SEM) analysis, XRD and Vickers microhardness measurements were conducted to characterize the samples. The irradiations were carried out with a 5 keV helium ion beam to fluences up to 5.0 x 10(21) ions/m(2) under 600 degrees C using the low-energy ion irradiation system. Transmission electron microscopy (TEM) study was performed to investigate the microstructural evolution in W-1 wt% Pr2O3 and W-1 wt% La2O3. At 1.0 x 10(20) He+/m(2), the average loops size of the W-1wt%Pr2O3 was 4.3 nm, much lower than W-1wt% La2O3 of 8.5 nm. However, helium bubbles were not observed throughout in both doped W materials. The effects of pre-irradiation with 1.0 x 10(21) He+/m(2) on trapping of injected deuterium in doped W was studied by thermal desorption spectrometry (TDS) technique using quadrupole mass spectrometer. Compared with the samples without He+ pre-irradiation, deuterium (D) retention of doped W materials increased after He+ irradiation, whose retention was unsaturated at the damage level of 1.0 x 10(22)D(2)(+)/m(2). The present results implied that irradiation effect of He+ ions must be taken into account to evaluate the deuterium retention in fusion material applications. (C) 2020 Korean Nuclear Society, Published by Elsevier Korea LLC. |
| WOS关键词 | RADIATION-DAMAGE ; ION-IRRADIATION ; HELIUM ; DEFORMATION ; TEMPERATURE ; BEHAVIOR ; ALLOYS ; PLASMA |
| 资助项目 | National Magnetic Confinement Fusion Program[2014GB121001] ; National Natural Science Foundation of China[51574101] ; National Natural Science Foundation of China[51474083] ; Fundamental Research Funds for the Central Universities[PA2018GDQT0010] ; 111 Project[B18018] ; Open Foundation of Key Laboratory of Advanced Functional Materials and Devices of the Anhui Province ; Double First Class enhancing independent innovation and social service capabilities of Hefei University of Technology[4500-411104/011] ; JSPS KAKENHI[JP20K03900] |
| WOS研究方向 | Nuclear Science & Technology |
| 语种 | 英语 |
| 出版者 | KOREAN NUCLEAR SOC |
| WOS记录号 | WOS:000582613900017 |
| 资助机构 | National Magnetic Confinement Fusion Program ; National Natural Science Foundation of China ; Fundamental Research Funds for the Central Universities ; 111 Project ; Open Foundation of Key Laboratory of Advanced Functional Materials and Devices of the Anhui Province ; Double First Class enhancing independent innovation and social service capabilities of Hefei University of Technology ; JSPS KAKENHI |
| 源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/104829]  |
| 专题 | 中国科学院合肥物质科学研究院 |
| 通讯作者 | Ding, Xiao-Yu; Wu, Yu-Cheng |
| 作者单位 | 1.Kyoto Univ, Inst Integrated Radiat & Nucl Sci, Osaka 5900494, Japan 2.Zhejiang Univ Technol, Inst Laser Adv Mfg, Hangzhou 310014, Peoples R China 3.Shenzhen Univ, Coll Optoelect Engn, Key Lab Optoelect Devices & Syst, Minist Educ & Guangdong Prov, Shenzhen 518060, Peoples R China 4.Hefei Univ Technol, Sch Mat Sci & Engn, Hefei 230009, Peoples R China 5.Key Lab Adv Funct Mat & Devices Anhui Prov, Hefei 230009, Peoples R China 6.Natl Local Joint Engn Res Ctr Nonferrous Met & Pr, Hefei 230009, Peoples R China 7.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China |
| 推荐引用方式 GB/T 7714 | Ding, Xiao-Yu,Xu, Qiu,Zhu, Xiao-yong,et al. Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation[J]. NUCLEAR ENGINEERING AND TECHNOLOGY,2020,52. |
| APA | Ding, Xiao-Yu.,Xu, Qiu.,Zhu, Xiao-yong.,Luo, Lai-Ma.,Huang, Jian-Jun.,...&Wu, Yu-Cheng.(2020).Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation.NUCLEAR ENGINEERING AND TECHNOLOGY,52. |
| MLA | Ding, Xiao-Yu,et al."Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation".NUCLEAR ENGINEERING AND TECHNOLOGY 52(2020). |
入库方式： OAI收割
来源：合肥物质科学研究院
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