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司太力合金涂层的制备及与液态铅铋相容性研究

Research on Preparation of Stellite Alloy Coating and Its Compatibility with Liquid Lead-Bismuth Eutectic Alloy

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【作者】 张天一吕沙沙阮章顺付晓刚龙斌陶柳秦博李正操

【Author】 ZHANG Tianyi;Lü Shasha;RUAN Zhangshun;FU Xiaogang;LONG Bin;TAO Liu;QIN Bo;LI Zhengcao;School of Materials Science and Engineering, Tsinghua University;College of Nuclear Science and Technology, Beijing Normal University;Reactor Engineering Technology Research Institute, China Institute of Atomic Energy;

【通讯作者】 吕沙沙;付晓刚;

【机构】 清华大学材料学院北京师范大学核科学与技术学院中国原子能科学研究院反应堆工程技术研究所

【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。

【Abstract】 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.

【关键词】 涂层铅铋腐蚀性能评估
【Key words】 coatinglead-bismuth corrosionperformance evaluation
【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)
  • 【文献出处】 材料开发与应用 ,Development and Application of Materials , 编辑部邮箱 ,2023年06期
  • 【分类号】TG174.4
  • 【下载频次】32
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