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

文献类型：期刊论文

作者Chen, Yiheng2; Long, Yunxiang2; Luo, Hongtai2; Xie, Ziyang2; Lin, Wenbin2; Guo, Liping2; Wang, Hui3; An, Xuguang4; Kong, Qingquan4; Zhang, WeiPing1
刊名JOURNAL OF NUCLEAR MATERIALS
出版日期2022-12-01
卷号571
ISSN号0022-3115
关键词Ferritic martensitic steel Silicon content Precipitate Irradiation damage Nanohardness
DOI10.1016/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.
WOS关键词HEAVY-ION DAMAGE ; MECHANICAL-PROPERTIES ; CORROSION-RESISTANCE ; STRUCTURAL-MATERIALS ; MARTENSITIC STEELS ; TENSILE PROPERTIES ; FERRITIC STEELS ; GRAIN-SIZE ; CLAM STEEL ; FE
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
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).

入库方式： OAI收割

来源：合肥物质科学研究院

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