摘要
铅冷快堆使用具有更高安全性的液态铅铋合金作为冷却剂,是颇具发展前景的先进四代堆型。本研究围绕耐铅铋腐蚀涂层,在奥氏体不锈钢基体上开展司太力合金涂层的制备,分析其组成成分和微观结构。开展涂层的铅铋腐蚀实验,分析其结构完整性、力学性能、表面氧化层及物相组成变化。通过微观结构和力学性能表征,评估司太力合金涂层的耐铅铋腐蚀性能,从而为铅铋快堆的工程应用提供理论支撑和技术支持。
The lead-bismuth fast reactor uses liquid lead-bismuth alloy as the coolant,which has high safety and promising development prospects as Generation Ⅳ.In this study,we mainly focus on the lead-bismuth corrosion resistant coatings.The Stellite alloy coatings are prepared on the austenitic stainless steel substrates,whose composition and microstructure are analyzed.The lead-bismuth corrosion resistance experiment of the coating is carried out to analyze its structural integrity,mechanical properties,surface oxide layer,and phase composition changes.The lead-bismuth corrosion resistance of the Stellite alloy coating is evaluated by characterizing the microstructure and mechanical properties to provide theoretical and technical support for the engineering application of the lead-bismuth fast reactors.
作者
张天一
吕沙沙
阮章顺
付晓刚
龙斌
陶柳
秦博
李正操
ZHANG Tianyi;LShasha;RUAN Zhangshun;FU Xiaogang;LONG Bin;TAO Liu;QIN Bo;LI Zhengcao(School of Materials Science and Engineering,Tsinghua University,Beijing 100084,China;College of Nuclear Science and Technology,Beijing Normal University,Beijing 100875,China;Reactor Engineering Technology Research Institute,China Institute of Atomic Energy,Beijing 102413,China)
出处
《材料开发与应用》
CAS
2023年第6期9-14,共6页
Development and Application of Materials
基金
国家原子能机构核材料技术创新中心合作项目(ICMW-2022-Y2)。
关键词
涂层
铅铋腐蚀
性能评估
coating
lead-bismuth corrosion
performance evaluation
