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Zr-4合金管冲击磨损性能及损伤机制研究 被引量:1

Impact Wear Properties and Wear Mechanism of Zr-4 Alloy Tube
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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.
出处 《润滑与密封》 CAS CSCD 北大核心 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)
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 nuclear power materials Zr-4 alloy nuclear fuel cladding tube impact wear wear mechanism
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