Fretting wear mechanism of nuclear fuel cladding tube under different tangential displacement

被引:0
|
作者
Li, Jialing [1 ]
Shen, Huoming [1 ]
Liao, Yehong [3 ]
Wang, Yuxing [1 ,2 ]
Jin, Songye [1 ]
Peng, Zhenxun [3 ]
Wang, Kaimo [1 ]
Ren, Qisen [3 ]
机构
[1] Southwest Jiaotong Univ, Sch Mech & Aerosp Engn, Chengdu 611756, Peoples R China
[2] Southwest Jiaotong Univ, Sch Mech Engn, Chengdu 611756, Peoples R China
[3] China Nucl Power Technol Res Inst Co Ltd, Dept ATF R&D, Shenzhen 518000, Peoples R China
基金
中国国家自然科学基金;
关键词
Fretting wear; Zr-1Nb alloy cladding tube; Grid-to-rod contact; Displacement amplitudes; Wear mechanism; BEHAVIOR; ALLOY; ROD; TEMPERATURE; IMPACT; FREQUENCY; AMPLITUDE; FRICTION; STEEL; WATER;
D O I
10.1016/j.nucengdes.2024.113567
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The fretting wear behavior of Zr-1Nb alloy cladding tubes under different tangential displacement amplitudes under grid-to-rod contact conditions was investigated. The dependence of the morphology of wear scars, microstructure, and wear mechanisms on the tangential displacement amplitudes was analyzed. The results indicate that as the tangential displacement amplitude increases, the fretting regime transitions from the mixed fretting regime to the gross slip regime gradually, moreover, the coefficient of friction initially increases and then decreases, while the wear volume and maximum wear depth gradually increase. In the mixed fretting regime, the primary wear mechanism is adhesive wear, whereas the primary wear mechanism in the gross slip regime is delamination. Moreover, the extent of oxidative wear becomes more severe while the tangential displacement amplitude is larger.
引用
收藏
页数:9
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