高温加压水环境下铬涂层覆层的摩擦磨损特性演变

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Jun Wang , Ke Li , Yuchun Wu , Yujie Xie , Jing Ni , Zefei Zhu , Zhenbing Cai
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引用次数: 0

摘要

铬基涂层是压水堆耐事故燃料包壳最简单、最易研究、最有前途的涂层。在这项工作中,使用了特殊的高温压水切向摩擦磨损设备进行实验研究。研究了高温高压水环境下循环次数对铬涂层覆层烧蚀磨损的影响,并揭示了磨损过程中涂层的演变特征。结果表明,随着循环次数的增加,Cr 覆层的主要磨损机理由粘着磨损转变为疲劳磨损,最后转变为磨料磨损和分层。在摩擦磨损过程中,疲劳磨损引起的裂纹是导致涂层失效的主要因素。此外,磨损过程中磨损碎屑在铬镀层表面积聚,形成致密的摩擦氧化层(釉层),使铬镀层在烧蚀磨损初期能保持完整的结构。摩擦过程中产生的剪切应力会加速材料的去除,而摩擦氧化层的存在可以起到一定的润滑作用。二者呈竞争关系,最终形成了磨损、氧化、再磨损的磨损循环机制。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

Evolution of fretting wear characteristics of Cr-coated cladding under high-temperature pressurized water environment

Evolution of fretting wear characteristics of Cr-coated cladding under high-temperature pressurized water environment
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.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
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.
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