Fretting wear behavior test and numerical simulation of Inconel 690 alloy
Author:
Affiliation:
1. School of Mechanical Engineering, Zhejiang University of Technology, Hangzhou, China
2. China Nuclear Power Operation Management Co. LTD, Jiaxing, China
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00223131.2023.2201597
Reference26 articles.
1. Modeling of Thermohydraulic Processes in a Steam Generator with Several Plugged Heat-Transfer Tubes
2. Review of the tube external condensation heat transfer characteristic of the passive containment cooling system in nuclear power plant
3. Heat transfer phenomenon and characteristics study of C-shaped tube with nucleate boiling in water tank
4. Fretting wear modeling of 3D and 2D Hertzian contacts with a third-body layer using a Winkler elastic foundation model
5. Evolution of fretting wear with the number of cycles on Inconel 690 steam generator tubes against AISI 420 steel under gross slip conditions
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