Impact-sliding wear response of 2.25Cr1Mo steel tubes:Experimental and semi-analytical method  

作　　者：Meigui YIN Thibaut CHAISE Liwen WANG Daniel NÉLIAS Minhao ZHU Zhenbing CAI 

机构地区：[1]Tribology Research Institute,Key Lab of Advanced Technologies of Materials,Southwest Jiaotong University,Chengdu 610031,China [2]Univ Lyon,INSA Lyon,CNRS,LaMCoS,UMR5259,Villeurbanne 69621,France [3]Research Institute of Dongfang Electric Corporation,Chengdu 611731,China

出　　处：《Friction》2022年第3期473-490,共18页摩擦（英文版）

基　　金：This study is supported by the National Natural Science Foundation of China(No.U1530136);Young Scientific Innovation Team of Science and Technology of Sichuan(No.2017TD0017);The author Meigui YIN acknowledges the financial support from the China Scholarship Council(CSC No.201907000021).

摘　　要：The impact-sliding wear behavior of steam generator tubes in nuclear power plants is complex owing to the dynamic nature of the mechanical response and self-induced tribological changes.In this study,the effects of impact and sliding velocity on the impact-sliding wear behavior of a 2.25Cr1Mo steel tube are investigated experimentally and numerically.In the experimental study,a wear test rig that can measure changes in the impact and friction forces as well as the compressive displacement over different wear cycles,both in real time,is designed.A semi-analytical model based on the Archard wear law and Hertz contact theory is used to predict wear.The results indicate that the impact dynamic effect by the impact velocity is more significant than that of the sliding velocity,and that both velocities affect the friction force and wear degree.The experimental results for the wear depth evolution agree well with the corresponding simulation predictions.

关 键 词：impact-sliding wear SEMI-ANALYTICAL 2.25Cr1Mo steel tube nuclear reactors 

分 类 号：TH117.1[机械工程—机械设计及理论] TM623[电气工程—电力系统及自动化]