中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
Microstructural evolution and hardening of W-ZrC, W-1Re-ZrC and W-3Re-ZrC alloys induced by He ions irradiation

文献类型:期刊论文

作者Fu, Y. J.1,2; Wang, H.1; Xie, Z. M.1; Liu, R.1; Wang, X. P.1; Fang, Q. F.1; Liu, C. S.1; Wu, X. B.1
刊名NUCLEAR MATERIALS AND ENERGY
出版日期2024-09-01
卷号40
关键词Tungsten He ion irradiation Dislocation loop Irradiation hardening
DOI10.1016/j.nme.2024.101729
通讯作者Xie, Z. M.(zmxie@issp.ac.cn) ; Wu, X. B.(xbwu@issp.ac.cn)
英文摘要Bulk W-0.5 wt%ZrC (W-ZrC), W-1 wt%Re-0.5 wt%ZrC (W-1Re-ZrC), and W-3 wt%Re-0.5 wt%ZrC (W-3Re-ZrC) alloys were prepared and exposed to He2+ 2+ ion irradiation with an incident energy of 500 keV at 400 degrees C. Post- irradiation analysis revealed the formation of He bubbles, with consistent number density and average size across all alloys. However, the W-3Re-ZrC alloy exhibited a notably higher density of dislocation loops within grain interiors compared to W-ZrC and W-1Re-ZrC. This led to a significant increase in the hardening rate of W3Re-ZrC to 61.5 %, nearly twice that of the other alloys. By considering the binding energies of He-vacancy, He- He, and Re-He, the formation and growth behavior of irradiation-induced defects, including He bubbles and dislocation loops, were also discussed. This work provides valuable insight into the relationships among Re alloying, He-induced defects, and irradiation hardening in Re-alloyed W materials, thus offering valuable guidance for the design of W-based plasma-facing materials.
WOS关键词ATOM-PROBE TOMOGRAPHY ; STRENGTHENED TUNGSTEN ; DISPLACEMENT DAMAGE ; POINT-DEFECTS ; HELIUM ; RE ; NANOCRYSTALLINE ; PRECIPITATION ; TEMPERATURE ; TRANSITION
资助项目National Natural Science Foundation of China[52325103] ; National Natural Science Foundation of China[12375260] ; National Natural Science Foundation of China[12192282] ; National Natural Science Foundation of China[U2341256] ; National Key Research and Development Program of China[2019YFE03110200] ; National Key Research and Development Program of China[2022YFE03110002] ; National Key Research and Development Program of China[2022YFE03140002] ; Strategic Priority Research Program of the Chinese Academy of Sciences[XDB0470303] ; HFIPS Director's Funds[BJPY2021A05] ; HFIPS Director's Funds[GGZX-GTCX-2023-11]
WOS研究方向Nuclear Science & Technology
语种英语
WOS记录号WOS:001307645200001
出版者ELSEVIER
资助机构National Natural Science Foundation of China ; National Key Research and Development Program of China ; Strategic Priority Research Program of the Chinese Academy of Sciences ; HFIPS Director's Funds
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/135061]  
专题中国科学院合肥物质科学研究院
通讯作者Xie, Z. M.; Wu, X. B.
作者单位1.Chinese Acad Sci, Inst Solid State Phys, Key Lab Mat Phys, HFIPS, Hefei 230031, Peoples R China
2.Univ Sci & Technol China, Hefei 230026, Peoples R China
推荐引用方式
GB/T 7714
Fu, Y. J.,Wang, H.,Xie, Z. M.,et al. Microstructural evolution and hardening of W-ZrC, W-1Re-ZrC and W-3Re-ZrC alloys induced by He ions irradiation[J]. NUCLEAR MATERIALS AND ENERGY,2024,40.
APA Fu, Y. J..,Wang, H..,Xie, Z. M..,Liu, R..,Wang, X. P..,...&Wu, X. B..(2024).Microstructural evolution and hardening of W-ZrC, W-1Re-ZrC and W-3Re-ZrC alloys induced by He ions irradiation.NUCLEAR MATERIALS AND ENERGY,40.
MLA Fu, Y. J.,et al."Microstructural evolution and hardening of W-ZrC, W-1Re-ZrC and W-3Re-ZrC alloys induced by He ions irradiation".NUCLEAR MATERIALS AND ENERGY 40(2024).

入库方式: OAI收割

来源:合肥物质科学研究院

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