Jun Wang , Ke Li , Yuchun Wu , Yujie Xie , Jing Ni , Zefei Zhu , Zhenbing Cai
{"title":"Evolution of fretting wear characteristics of Cr-coated cladding under high-temperature pressurized water environment","authors":"Jun Wang , Ke Li , Yuchun Wu , Yujie Xie , Jing Ni , Zefei Zhu , Zhenbing Cai","doi":"10.1016/j.nucengdes.2024.113665","DOIUrl":null,"url":null,"abstract":"<div><div>The Cr (chromium) based coating is the most simple, studied, and promising coating for the accident-tolerant fuel cladding of pressurized water reactors. In this work, special tangential fretting wear equipment in high-temperature pressurized water was used to carry out experimental research. The influence of cycles on the fretting wear of Cr-coated cladding under high-temperature and high-pressure water environment was investigated, and the evolution characteristic of the coating during the wear process was revealed. The results show that with the increase in cycles, the main wear mechanism of Cr cladding changes from adhesive wear to fatigue wear, and finally to abrasive wear and delamination. Crack caused by fatigue wear during fretting wear was the main factor leading to the failure of the coating. In addition, wear debris accumulated on the surface of the Cr coating during wear and formed a dense friction oxidative layer (glaze layer), so that the Cr coating can maintain a complete structure in the early stage of fretting wear. The shear stress generated by the friction process will accelerate the material removal, and the existence of a friction oxidative layer can play a certain role in lubrication. The two were in a competitive relationship and finally formed a wear cycle mechanism of wear, oxidation, and re-wear.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"430 ","pages":"Article 113665"},"PeriodicalIF":1.9000,"publicationDate":"2024-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549324007659","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
The Cr (chromium) based coating is the most simple, studied, and promising coating for the accident-tolerant fuel cladding of pressurized water reactors. In this work, special tangential fretting wear equipment in high-temperature pressurized water was used to carry out experimental research. The influence of cycles on the fretting wear of Cr-coated cladding under high-temperature and high-pressure water environment was investigated, and the evolution characteristic of the coating during the wear process was revealed. The results show that with the increase in cycles, the main wear mechanism of Cr cladding changes from adhesive wear to fatigue wear, and finally to abrasive wear and delamination. Crack caused by fatigue wear during fretting wear was the main factor leading to the failure of the coating. In addition, wear debris accumulated on the surface of the Cr coating during wear and formed a dense friction oxidative layer (glaze layer), so that the Cr coating can maintain a complete structure in the early stage of fretting wear. The shear stress generated by the friction process will accelerate the material removal, and the existence of a friction oxidative layer can play a certain role in lubrication. The two were in a competitive relationship and finally formed a wear cycle mechanism of wear, oxidation, and re-wear.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.