Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR

doi:10.1007/s40195-022-01496-2

IMR OpenIR

	Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR
	Zhang, Yusheng 1,2; Lai, Jiang 3; Ming, Hongliang 1,2; Gao, Lixia 3; Wang, Jianqiu 2; Han, En-Hou 2
通讯作者	Ming, Hongliang(hlming12s@imr.ac.cn) ; Wang, Jianqiu(wangjianqiu@imr.ac.cn)
	2022-12-20
发表期刊	ACTA METALLURGICA SINICA-ENGLISH LETTERS
ISSN	1006-7191
页码	16
摘要	The effect of normal force on fretting wear behavior of zirconium alloy tube mated with grid dimple in simulated primary water of pressurized water reactor nuclear power plant was investigated. Results showed that the maximum wear depth, wear volume and wear coefficient of Zr alloy tube in simulated primary water at 315 degrees C gradually increased with increasing normal force, while the friction coefficient gradually decreased. Fretting process could be divided into four stages according to the variation of friction coefficient during test. When normal force exceeds 30 N, the fretting regime would transition from gross slip regime to partial slip regime after 3 x 10(7) cycles. Delamination was aggravated with increasing normal force, while abrasive wear became slighter. A thicker third-body layer with monoclinic ZrO2 was formed by the tribo-sintering mechanism under higher normal force. In addition, the schematic evolution processes of delamination and third-body layer formation were displayed according to morphology observation.
关键词	Zirconium alloy tube Fretting wear Grid-to-rod High-temperature pressurized water Normal force
资助者	Youth Innovation Promotion Assessment CAS ; IMR Innovation Fund ; open-ended fund of the CAS Key laboratory of Nuclear Materials and Safety Assessment (Institute of Metal Research, Chinese Academy of Sciences, China)
DOI	10.1007/s40195-022-01496-2
收录类别	SCI
语种	英语
资助项目	Youth Innovation Promotion Assessment CAS[2022187] ; IMR Innovation Fund[2021-PY10] ; open-ended fund of the CAS Key laboratory of Nuclear Materials and Safety Assessment (Institute of Metal Research, Chinese Academy of Sciences, China)[2020NMSAKF01]
WOS研究方向	Metallurgy & Metallurgical Engineering
WOS类目	Metallurgy & Metallurgical Engineering
WOS记录号	WOS:000901696000001
出版者	CHINESE ACAD SCIENCES, INST METAL RESEARCH
引用统计	被引频次：12[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/321006/175820
专题	中国科学院金属研究所
通讯作者	Ming, Hongliang; Wang, Jianqiu
作者单位	1.Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Peoples R China 2.Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China 3.Nucl Power Inst China, Chengdu 610213, Peoples R China
推荐引用方式 GB/T 7714	Zhang, Yusheng,Lai, Jiang,Ming, Hongliang,et al. Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR[J]. ACTA METALLURGICA SINICA-ENGLISH LETTERS,2022:16.
APA	Zhang, Yusheng,Lai, Jiang,Ming, Hongliang,Gao, Lixia,Wang, Jianqiu,&Han, En-Hou.(2022).Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR.ACTA METALLURGICA SINICA-ENGLISH LETTERS,16.
MLA	Zhang, Yusheng,et al."Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR".ACTA METALLURGICA SINICA-ENGLISH LETTERS (2022):16.