| Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR | |
| Zhang, Yusheng1,2; Lai, Jiang3; Ming, Hongliang1,2; Gao, Lixia3; Wang, Jianqiu2; Han, En-Hou2 | |
| Corresponding Author | Ming, Hongliang(hlming12s@imr.ac.cn) ; Wang, Jianqiu(wangjianqiu@imr.ac.cn) |
| 2022-12-20 | |
| Source Publication | ACTA METALLURGICA SINICA-ENGLISH LETTERS
 |
| ISSN | 1006-7191 |
| Pages | 16 |
| Abstract | 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. |
| Keyword | Zirconium alloy tube Fretting wear Grid-to-rod High-temperature pressurized water Normal force |
| Funding Organization | 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 |
| Indexed By | SCI |
| Language | 英语 |
| Funding Project | 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 Research Area | Metallurgy & Metallurgical Engineering |
| WOS Subject | Metallurgy & Metallurgical Engineering |
| WOS ID | WOS:000901696000001 |
| Publisher | CHINESE ACAD SCIENCES, INST METAL RESEARCH |
| Citation statistics | |
| Document Type | 期刊论文 |
| Identifier | http://ir.imr.ac.cn/handle/321006/175820 |
| Collection | 中国科学院金属研究所 |
| Corresponding Author | Ming, Hongliang; Wang, Jianqiu |
| Affiliation | 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 |
| Recommended Citation 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. |
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