Fretting wear between Alloy 690 and 405 stainless steel in high temperature pressurized water with different normal force and displacement

doi:10.1016/j.jnucmat.2019.151930

CORC > 金属研究所 > 中国科学院金属研究所

	Fretting wear between Alloy 690 and 405 stainless steel in high temperature pressurized water with different normal force and displacement
	Ming, Hongliang 2; Liu, Xingchen 1,2; Lai, Jiang 3; Wang, Jianqiu 2; Gao, Lixia 3; Han, En-Hou 2
刊名	JOURNAL OF NUCLEAR MATERIALS
	2020-02-01
卷号	529 页码:14
关键词	Alloy 690 Fretting wear Normal force Displacement
ISSN号	0022-3115
DOI	10.1016/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
出版者	ELSEVIER
WOS记录号	WOS:000506622500023
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
内容类型	期刊论文
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.Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Liaoning, Peoples R China 2.Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, 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.