Zr-4合金管冲击磨损性能及损伤机制研究  

Impact Wear Properties and Wear Mechanism of Zr-4 Alloy Tube

作　　者：杨凯[1] 任平弟[1] 张晓宇[1] 李长香[2] 

机构地区：[1]西南交通大学牵引动力国家重点实验室摩擦学研究所,四川成都610031 [2]中国核动力研究设计院设计所,四川成都610041

出　　处：《润滑与密封》2016年第4期12-17,共6页Lubrication Engineering

基　　金：国家自然科学基金项目(51075324);中央高校基本科研业务费专项资金科技创新项目(2682014cx037)

摘　　要：在JDTRI-50冲击磨损试验机上，在冲击频率为10Hz，冲击载荷为10～40N，冲击次数为5万～10万次条件下，对Zr-4合金管试件与Inconel718镍合金板配副进行冲击磨损试验，研究核电燃料棒包壳管材Zr-4合金的冲击磨损性能及损伤机制。结果表明：冲击次数一定时，随着冲击载荷的增加磨痕宽度明显增加，损伤加重；载荷一定时，随着冲击次数增加，Zr-4合金管冲击损伤面积和深度增大；磨损面磨屑含氧量随冲击次数增加，经历较快增加、增速放缓及基本稳定的变化过程；Zr-4合金管冲击磨损的损伤机制主要表现为塑性变形、磨损氧化和疲劳剥落的逐次出现、相互转换和协同作用。The impact wear tests of Zr-4 alloy tubes against Inconel718 Nickel alloy plates were carried out on a small load impact wear test machine JDTRI-50 under the impact frequency of 10 Hz,the impact loads from 10 N to 40 N respectively,the impact times from 50 000 to 100 000. The impact wear behavior and mechanism of damage of the nuclear fuel rod cladding Zr-4 alloy tube were studied. The results show that,with the increasing of impact load,the wear scar width is increased and impact damage is aggravated at fixed impact times; with the increasing of impact times,the impact damage area and depth of Zr-4 alloy cladding tube is increased at fixed load. The oxygen content of wear debris shows a process of change of a rapid increase,a slowdown and a basic stability in oxygen content. The mechanism of impact wear mainly includes the successive emergence,mutual conversion and synergistic effect of plastic deformation,oxidation wear and fatigue spalling.

关 键 词：核电材料 ZR-4合金 核燃料包壳管 冲击磨损 损伤机制 

分 类 号：TH117.1[机械工程—机械设计及理论]