切向位移对Cr涂层Zr-1Nb合金包壳微动磨损的影响  

Effect of Tangential Displacement on Fretting Wear of Cr-coated Zr-1Nb Alloy Cladding Tube

作　　者：李加玲 沈火明[1] 廖业宏 王宇星 任啟森 彭振驯 LI Jialing;SHEN Huoming;LIAO Yehong;WANG Yuxing;REN Qisen;PENG Zhenxun(College of Mechanics and Aeronautics,Southwest Jiaotong University,Chengdu 610031,China;Department of Nuclear Fuel&Material,China Nuclear Power Technology Research Institute Co.,Ltd.,Shenzhen 518026,China;College of Mechanical Engineering,Southwest Jiaotong University,Chengdu 610031,China)

机构地区：[1]西南交通大学力学与航空航天学院,成都610031 [2]中广核研究院有限公司核燃料与材料研究所,深圳518026 [3]西南交通大学机械工程学院,成都610031

出　　处：《中国表面工程》2024年第4期303-312,共10页China Surface Engineering

基　　金：四川省自然科学基金(2022NSFSC2003,2023NSFSC1300);中央高校基本科研业务费专项经费(2682022CX056)。

摘　　要：随着核电技术更新迭代,由于传统Zr合金包壳存在安全性能缺陷,核燃料组件安全面临严峻挑战,探索开发新型核燃料包壳管成为核电安全防护领域的重点研究。以Cr涂层Zr-1Nb合金包壳管(改良型ATF材料)为研究对象,探究切向位移对Cr涂层Zr-1Nb合金包壳管微动磨损行为及磨损机理的影响。采用白光干涉仪表征出Cr涂层Zr-1Nb合金包壳管表面磨痕的三维形貌,对Cr涂层Zr-1Nb合金包壳管表面磨痕的截面轮廓以及磨损深度进行测算。通过扫描电子显微镜(SEM)和能谱仪(EDS)对表面磨痕的微观形貌以及元素组成进行表征。结果表明:随着切向位移增加最大磨损深度随之增加,微动运行状态由部分滑移逐渐转变为完全滑移,Cr涂层Zr-1Nb合金包壳管表面的磨屑黏着现象逐渐减弱,磨损机理由黏着磨损转变为剥层磨损。所有试验中Cr涂层Zr-1Nb合金包壳管存在明显的氧化磨损。从微观角度探索了接触模型为GTR构型的改良型ATF包壳材料微动磨损机理以及微动磨损行为,制备的Cr涂层能够提高Zr-1Nb合金包壳管的微动磨损性能,有效延长包壳管的服役寿命。Zr alloys are widely used as fuel rod cladding materials in nuclear reactors because of their small neutron absorption cross-section,high strength at high temperatures,and strong corrosion resistance.With the new iteration of nuclear power technology,the traditional Zr alloy cladding tube has exposed serious defects in safety performance,and the safety of nuclear fuel assemblies has been severely challenged.Currently,the exploration and development of new ATF materials have focused on nuclear reactor safety.The physical and chemical properties of the substrate can be improved by spraying a wear-resistant coating on the Zr alloy surface.The Cr coating has excellent high-temperature wear resistance and is currently the most important coating material.However,there are few reports on the fretting wear properties of Cr-coated Zr alloy cladding tubes and dimple structures that are in actual use in nuclear reactors.In this paper,the effect of tangential displacement on the fretting wear mechanism and wear properties of Cr-coated Zr-1Nb alloy coated tubes are investigated at room temperature.Scanning electron microscopy and energy-dispersive spectrometry were used to observe the surface morphology and elemental composition of the wear marks,respectively.The wear volume and maximum wear depth of the wear marks were measured using a white light interferometer.The results showed that the surface material underwent repeated alternating loads,resulting in cracks within the microstructure that eventually expanded to form wear debris.The tangential displacement amplitude is the key factor affecting fretting wear.As the amplitude increased,the wear debris was discharged more easily,the direct contact area between the samples increased,the sliding zone increased,and the fretting running status changed from a mixed fretting regime to a gross slip regime.This resulted in more evident delamination wear,oxidation wear,and increased surface stress,which led to the intensification of wear.When the tangential displacement is small,the

关 键 词：Cr涂层Zr-1Nb合金包壳管 黏着磨损 剥层磨损 完全滑移 

分 类 号：TL344[核科学技术—核技术及应用]