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Impact-sliding wear response of 2.25Cr1Mo steel tubes:Experimental and semi-analytical method
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作者 Meigui YIN thibaut chaise +3 位作者 Liwen WANG Daniel NÉLIAS Minhao ZHU Zhenbing CAI 《Friction》 SCIE EI CAS CSCD 2022年第3期473-490,共18页
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 im... 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. 展开更多
关键词 impact-sliding wear SEMI-ANALYTICAL 2.25Cr1Mo steel tube nuclear reactors
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