中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
Fretting wear between Alloy 690 and 405 stainless steel in high temperature pressurized water with different normal force and displacement

文献类型:期刊论文

作者Ming, Hongliang1; Liu, Xingchen1,2; Lai, Jiang3; Wang, Jianqiu1; Gao, Lixia3; Han, En-Hou1
刊名JOURNAL OF NUCLEAR MATERIALS
出版日期2020-02-01
卷号529页码:14
关键词Alloy 690 Fretting wear Normal force Displacement
ISSN号0022-3115
DOI10.1016/j.jnucmat.2019.151930
通讯作者Wang, Jianqiu(wangjianqiu@imr.ac.cn)
英文摘要As fretting wear has become one of the main failure mode of Alloy 690 tube in steam generators and is significantly affected by normal force and displacement, the fretting wear behavior of Alloy 690 with different normal force and displacement is studied in high temperature pressurized water. The coefficient of friction, wear volume and maximum wear depth decrease with the increasing of the normal force, while they increase with the increasing of displacement. In addition, the wear mechanism and wear damage are also significantly affected by the applied normal force and displacement. Wear coefficient and energy wear coefficient are calculated respectively. Energy wear coefficient may be a more precise parameter than wear coefficient to describe the fretting wear process. (C) 2019 Elsevier B.V. All rights reserved.
资助项目Natural Science Foundation of Liaoning Province[20180540076] ; CAS Key laboratory of Nuclear Materials and Safety Assessment (Institute of Metal Research, Chinese Academy of Sciences, China)[2019NMSAKF02] ; National Natural Science Foundation of China[51771211]
WOS研究方向Materials Science ; Nuclear Science & Technology
语种英语
WOS记录号WOS:000506622500023
出版者ELSEVIER
资助机构Natural Science Foundation of Liaoning Province ; CAS Key laboratory of Nuclear Materials and Safety Assessment (Institute of Metal Research, Chinese Academy of Sciences, China) ; National Natural Science Foundation of China
源URL[http://ir.imr.ac.cn/handle/321006/136722]  
专题金属研究所_中国科学院金属研究所
通讯作者Wang, Jianqiu
作者单位1.Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China
2.Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Liaoning, Peoples R China
3.Nucl Power Inst China, Chengdu 610213, Sichuan, Peoples R China
推荐引用方式
GB/T 7714
Ming, Hongliang,Liu, Xingchen,Lai, Jiang,et al. Fretting wear between Alloy 690 and 405 stainless steel in high temperature pressurized water with different normal force and displacement[J]. JOURNAL OF NUCLEAR MATERIALS,2020,529:14.
APA Ming, Hongliang,Liu, Xingchen,Lai, Jiang,Wang, Jianqiu,Gao, Lixia,&Han, En-Hou.(2020).Fretting wear between Alloy 690 and 405 stainless steel in high temperature pressurized water with different normal force and displacement.JOURNAL OF NUCLEAR MATERIALS,529,14.
MLA Ming, Hongliang,et al."Fretting wear between Alloy 690 and 405 stainless steel in high temperature pressurized water with different normal force and displacement".JOURNAL OF NUCLEAR MATERIALS 529(2020):14.

入库方式: OAI收割

来源:金属研究所

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