摘要
为对多弧离子镀技术制备锆合金表面Cr涂层的耐高温氧化性能进行系统评价,对Cr涂层在水蒸气环境中的氧化行为进行研究。采用同步热分析仪获取Cr涂层在800~1400℃的氧化增重数据、X射线衍射仪分析相结构、扫描电子显微镜分析表面形貌和横截面各膜层厚度、能谱仪分析元素分布。结果表明,1200℃水蒸气氧化后Cr涂层表面生成了致密的保护膜,氧化后膜基界面结合质量良好,且锆基体上残留有一定量的Cr涂层;在1300℃水蒸气环境中Cr涂层短时间内对基体具有保护作用,1400℃时Cr涂层会迅速失去其保护效果。因此,锆合金表面Cr涂层具有优异的抗高温氧化性能,1200℃长时间高温水蒸气氧化后仍对锆基体具有较好的保护作用。
For systematic review of the high-temperature oxidation resistance of Cr-coated Zirconium alloy fabricated by multi-arc ion plating,the oxidation behavior during the steam oxidation of Cr coating at 800-1400°C was studied.The oxidation weight gains were obtained by simultaneous thermal analyzer.The X-ray diffractometer was used to analyze the phase structure,the scanning electron microscope was used to analyze the surface morphology and thickness of each film in cross section,and the energy dispersive spectrometer was used to analyze the element distribution.The dense Cr_2O_(3) scales were formed on Cr coating after the steam oxidation at 1200℃,and the good interfacial bonding quality were observed between coating and substrate,as well as the residual Cr coating on Zr substrate were remained,and the residual Cr coating on Zr substrate were remained.The Cr coating could protect substrate for a short time at 1300℃ steam,but quickly lost its protection at 1400℃ steam.The Cr-coated Zirconium alloy has excellent high temperature oxidation resistance,and it still has good protection on substrate after the steam oxidation at 1200℃.
作者
杨红艳
吕俊男
张瑞谦
韦天国
Yang Hongyan;Lyu Junnan;Zhang Ruiqian;Wei Tianguo(Science and Technology on Reactor Fuel and Materials Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2023年第S01期168-175,共8页
Nuclear Power Engineering
基金
国家联合自然基金项目号(U21B2058)。
关键词
Cr涂层
水蒸气氧化
表面形貌
氧化速率
Cr coating
Steam oxidation
Surface morphology
Oxidation rate
