Effects of different silicon content on irradiation defects and hardening in 9Cr ferritic/martensitic steel

doi:10.1016/j.jnucmat.2022.154026

	Effects of different silicon content on irradiation defects and hardening in 9Cr ferritic/martensitic steel
	Chen, Yiheng 2; Long, Yunxiang 2; Luo, Hongtai 2; Xie, Ziyang 2; Lin, Wenbin 2; Guo, Liping 2; Wang, Hui 3; An, Xuguang 4; Kong, Qingquan 4; Zhang, WeiPing 1
刊名	JOURNAL OF NUCLEAR MATERIALS
	2022-12-01
卷号	571
关键词	Ferritic martensitic steel Silicon content Precipitate Irradiation damage Nanohardness
ISSN号	0022-3115
DOI	10.1016/j.jnucmat.2022.154026
通讯作者	Guo, Liping(guolp@whu.edu.cn) ; Wang, Hui(qinghe5525@163.com)
英文摘要	In order to explore the effect of silicon (Si) content on the irradiation behavior of ferritic/martensitic (F/M) steel, 9Cr F/M steel with Si of 0, 0.4%, 0.7%, and 1.0% in weight percent were prepared. All speci-mens were irradiated with 2.4 MeV iron ions at 550 degrees C to the fluence of 6.41 x 10 16 ions cm -2, corre-sponding to a peak damage dose of 70 dpa. Transmission electron microscopy (TEM) was used to charac-terize the microstructure of the alloys before and after irradiation, and nanoindentation tests were used to assess the irradiation hardening. The addition of Si inhibited the growth of both M 23 C 6 and MX pre-cipitates and promoted the nucleation of MX precipitates, and the nucleation of the M 23 C 6 precipitates was inhibited when the added Si was less than 0.7 wt.%, indicating that the precipitates can be regu-lated by Si content. The martensite lath width and the packet size of 0.4 wt.% Si content alloys are the largest and then decrease with the increase of Si content. As the Si content increases, the average size of dislocation loops decreases while the number density increases. Alloys without Si have the smallest void number density, followed by alloys with 0.7 wt.%, 0.4 wt.%, and 1.0 wt.% Si content. The hardness of the unirradiated alloy increased with the increase of Si content. After irradiation, the most severe radiation hardening occurred in the 0.4 wt.% Si alloy and the lowest in the 0.7 wt.% Si alloy.(c) 2022 Elsevier B.V. All rights reserved.
资助项目	National Natural Science Foundation of China[12175221] ; National Natural Science Foundation of China[11975170] ; National Magnetic Confinement Fusion Energy Research Project[2022YFE03110000]
WOS关键词	HEAVY-ION DAMAGE ; MECHANICAL-PROPERTIES ; CORROSION-RESISTANCE ; STRUCTURAL-MATERIALS ; MARTENSITIC STEELS ; TENSILE PROPERTIES ; FERRITIC STEELS ; GRAIN-SIZE ; CLAM STEEL ; FE
WOS研究方向	Materials Science ; Nuclear Science & Technology
语种	英语
出版者	ELSEVIER
WOS记录号	WOS:000872389200008
资助机构	National Natural Science Foundation of China ; National Magnetic Confinement Fusion Energy Research Project
内容类型	期刊论文
源URL	[http://ir.hfcas.ac.cn:8080/handle/334002/129819]
专题	中国科学院合肥物质科学研究院
通讯作者	Guo, Liping; Wang, Hui
作者单位	1.Hebei Univ Engn, Sch Math & Phys, Handan 056038, Hebei, Peoples R China 2.Wuhan Univ, Hubei Nucl Solid Phys Key Lab, Key Lab Artificial Microand Nanostruct, Minist Educ, Wuhan 430072, Peoples R China 3.Nucl Power Inst China, Sci & Technol Reactor Fuel & Mat Lab, Chengdu 610041, Peoples R China 4.Chengdu Univ, Inst Adv Study, Interdisciplinary Mat Res Ctr, Chengdu 610106, Peoples R China 5.Chinese Acad Sci, Inst Solid State Phys, Key Lab Mat Phys, Hefei 230031, Peoples R China 6.Chinese Acad Sci, Inst Geochem, Ctr Lunar & Planetary Sci, Guiyang 266071, Peoples R China
推荐引用方式 GB/T 7714	Chen, Yiheng,Long, Yunxiang,Luo, Hongtai,et al. Effects of different silicon content on irradiation defects and hardening in 9Cr ferritic/martensitic steel[J]. JOURNAL OF NUCLEAR MATERIALS,2022,571.
APA	Chen, Yiheng.,Long, Yunxiang.,Luo, Hongtai.,Xie, Ziyang.,Lin, Wenbin.,...&Wen, Yuanyun.(2022).Effects of different silicon content on irradiation defects and hardening in 9Cr ferritic/martensitic steel.JOURNAL OF NUCLEAR MATERIALS,571.
MLA	Chen, Yiheng,et al."Effects of different silicon content on irradiation defects and hardening in 9Cr ferritic/martensitic steel".JOURNAL OF NUCLEAR MATERIALS 571(2022).