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。
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.
作者
皮立新
胡勇
涂蒙河
杨明馨
王辉
PI Lixin;HU Yong;TU Menghe;YANG Mingxin;WANG Hui(China Institute of Atomic Energy,Beijing 102413,China)
出处
《腐蚀与防护》
CAS
北大核心
2021年第2期37-41,共5页
Corrosion & Protection
关键词
压水堆燃料包壳
ZR-4合金
酸洗
磨蚀
pressurized water reactor(PWR)fuel cladding
Zr-4 alloy
picking
wear and corrosion