Effect of Pickling on Fretting Wear and Corrosion Behavior of Zr-4 Alloy
摘 要
在高温高压水环境中对压水堆燃料包壳Zr-4合金开展了微动磨蚀试验。利用三维白光干涉仪、光学显微镜、扫描电镜、能谱等分析了微动磨蚀试验后试样的三维轮廓、表面形貌和化学成分。结果表明:酸洗和普洗Zr-4合金的磨蚀系数分别为6.26×10-16 Pa-1和3.3×10-16 Pa-1;Zr-4合金的损伤机制主要为黏着磨蚀损伤,同时存在塑性变形损伤;表面酸洗去除了材料加工处理时表面形成的硬化层,使材料表面更易划伤,从而降低材料的耐磨蚀性能。
Abstract
Fretting wear and corrosion test was performed to Zr-4 alloy for pressurized water reactor (PWR) fuel cladding in a water environment of high temperature and high pressure. The 3D profile, surface morphology and chemical composition of the samples after fretting wear and corrosion tests were analyzed by 3D white light interferometer, optical microscopy, scanning electron microscopy (SEM) and energy dispersive X-ray spectrometry (EDS). The results show that the wear and corrosion coefficients of the Zr-4 alloy with and without pickling were 6.26×10-16 Pa-1 and 3.3×10-16 Pa-1 respectively. Adhesion and abrasion was the main damage mechanism for the Zr-4 alloy and plastic deformation was also found. Surface pickling removed the hardened layer forming on the surface of the material during processing, making the surface of the material more prone to scratch, thus reducing the wear and corrosion resistance of the material.
中图分类号 TG146 DOI 10.11973/fsyfh-202102007
所属栏目 试验研究
基金项目
收稿日期 2019/4/28
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联系人作者皮立新(pilixin@sina.cn)
引用该论文: PI Lixin,HU Yong,TU Menghe,YANG Mingxin,WANG Hui. Effect of Pickling on Fretting Wear and Corrosion Behavior of Zr-4 Alloy[J]. Corrosion & Protection, 2021, 42(2): 37
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参考文献
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【2】JOULIN T P,GUÉROUT F M,LINA A,et al. Effects of loading conditions and types of motion on pwr fuel rod cladding wear[C]//Proceedings of ASME International Mechanical Engineering Congress and Exposition.[S.l]:[s.n.],2002:1011-1018.
【3】LEE Y H,KIM H K,JUNG Y H. Effect of impact frequency on the wear behavior of spring-supported tubes in room and high temperature distilled water[J]. Wear,2005,259:329-336.
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【5】KIM H K,LEE Y H,LEE K H. On the geometry of the fuel rod supports concerning a fretting wear failure[J]. Nuclear Engineering and Design,2008,238(12):3321-3330.
【6】LAI P,ZHANG H,ZHANG L F,et al. Effect of micro-arc oxidation on fretting wear behavior of zirconium alloy exposed to high temperature water[J]. Wear,2019,424/425:53-61.
【7】LAZAREVIC S,LU R Y,FAVEDE C,et al. Investigating grid-to-rod fretting wear of nuclear fuel claddings using a unique autoclave fretting rig[J]. Wear,2018,412/413:30-37.
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