Effect of aluminum content on dislocation loops in model FeCrAl alloys

doi:10.1016/j.nme.2019.100718

IMR OpenIR

	Effect of aluminum content on dislocation loops in model FeCrAl alloys
	Zhou, Xiong 1,2; Guo, Liping 1,2; Wei, Yaxia 1,2; Wang, Hui 3; Chen, Cheng 1,2; Chen, Yiheng 1,2; Zhang, Weiping 1,2; Liu, Shi 4; Liu, Renduo 5; Mo, Shaobo 6
通讯作者	Guo, Liping(guolp@whu.edu.cn) ; Wang, Hui(qinghe5525@163.com)
	2019-12-01
发表期刊	NUCLEAR MATERIALS AND ENERGY
卷号	21 页码:7
摘要	Five 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.
关键词	FeCrAl alloy Dislocation loops Radiation damage Accident tolerant fuel cladding
资助者	National Natural Science Foundation of China
DOI	10.1016/j.nme.2019.100718
收录类别	SCI
语种	英语
资助项目	National Natural Science Foundation of China[11775162] ; National Natural Science Foundation of China[51801194] ; National Natural Science Foundation of China[11975170]
WOS研究方向	Nuclear Science & Technology
WOS类目	Nuclear Science & Technology
WOS记录号	WOS:000500930900012
出版者	ELSEVIER
引用统计	被引频次：19[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/136179
专题	中国科学院金属研究所
通讯作者	Guo, Liping; Wang, Hui
作者单位	1.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
推荐引用方式 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.