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Effect of aluminum content on dislocation loops in model FeCrAl alloys
Zhou, Xiong1,2; Guo, Liping1,2; Wei, Yaxia1,2; Wang, Hui3; Chen, Cheng1,2; Chen, Yiheng1,2; Zhang, Weiping1,2; Liu, Shi4; Liu, Renduo5; Mo, Shaobo6
Corresponding AuthorGuo, Liping(guolp@whu.edu.cn) ; Wang, Hui(qinghe5525@163.com)
2019-12-01
Source PublicationNUCLEAR MATERIALS AND ENERGY
Volume21Pages:7
AbstractFive kinds of iron-chromium-aluminum (FeCrAl) alloy samples with different contents of aluminum (Al)-Fe-12Cr, Fe-12Cr-2Al, Fe-12Cr-4Al, Fe-12Cr-6Al, and Fe-12Cr-8Al-were designed and prepared. All samples were then irradiated with 200 keV argon ions (Ar2+) to the fluence of 9.3 x 10(14) ions cm(-2) at 330C. The formations of dislocation loops induced by Ar2+ irradiation in these alloys were investigated by transmission electron microscopy. Both of a/2 < 111 > and a <100 > dislocation loops were generated in all samples. The sizes of both a/2 < 111 > and a < 100 > dislocation loops decreased and total volume number densities increased with increasing Al content of the samples. The proportion of a/2 <111 > dislocation loops decreased first and then increased with Al content, and the ratio of a/2 < 111 > to a < 100 > average loop size increased first and then decreased with Al content. The experiment results indicate that the increase of Al content in alloys can enhance the nucleation and inhibit the growth of dislocation loops, the interaction between a/2 < 111 > and a < 100 > dislocation loops is affected by the Al content in alloys as well. The difference in dislocation loops in FeCrAl alloys with different Al contents after Ar2+ irradiation can be explained by the pinning of dislocation loops by the Al atoms.
KeywordFeCrAl alloy Dislocation loops Radiation damage Accident tolerant fuel cladding
Funding OrganizationNational Natural Science Foundation of China
DOI10.1016/j.nme.2019.100718
Indexed BySCI
Language英语
Funding ProjectNational Natural Science Foundation of China[11775162] ; National Natural Science Foundation of China[51801194] ; National Natural Science Foundation of China[11975170]
WOS Research AreaNuclear Science & Technology
WOS SubjectNuclear Science & Technology
WOS IDWOS:000500930900012
PublisherELSEVIER
Citation statistics
Cited Times:2[WOS]   [WOS Record]     [Related Records in WOS]
Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/136179
Collection中国科学院金属研究所
Corresponding AuthorGuo, Liping; Wang, Hui
Affiliation1.Wuhan Univ, Key Lab Artificial Micro & Nanostruct, Hubei Nucl Solid Phys Key Lab, Minist Educ, Wuhan 430072, Hubei, Peoples R China
2.Wuhan Univ, Sch Phys & Technol, Wuhan 430072, Hubei, Peoples R China
3.Nucl Power Inst China, Sci & Technol Reactor Fuel & Mat Lab, Chengdu 610041, Sichuan, Peoples R China
4.Chinese Acad Sci, Inst Met Res, Shenyang 110016, Liaoning, Peoples R China
5.Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China
6.Wuhan Univ, Anal & Testing Ctr, Wuhan 430072, Hubei, Peoples R China
Recommended Citation
GB/T 7714
Zhou, Xiong,Guo, Liping,Wei, Yaxia,et al. Effect of aluminum content on dislocation loops in model FeCrAl alloys[J]. NUCLEAR MATERIALS AND ENERGY,2019,21:7.
APA Zhou, Xiong.,Guo, Liping.,Wei, Yaxia.,Wang, Hui.,Chen, Cheng.,...&Mo, Shaobo.(2019).Effect of aluminum content on dislocation loops in model FeCrAl alloys.NUCLEAR MATERIALS AND ENERGY,21,7.
MLA Zhou, Xiong,et al."Effect of aluminum content on dislocation loops in model FeCrAl alloys".NUCLEAR MATERIALS AND ENERGY 21(2019):7.
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