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磁控溅射法制备锆合金包壳Cr涂层

Magnetron sputtered Chromium coating for zirconium alloy fuel claddings

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【作者】 王永利刘实熊良银

【Author】 WANG Yong-li;LIU Shi;XIONG Liang-yin;Institute of Metal Research,Chinese Academy Science;CAS Key Laboratory of Nuclear Materials and Safety Assessment;

【机构】 中国科学院金属研究所中国科学院核用材料与安全评价重点实验室

【摘要】 Cr涂层锆合金管相比现有锆合金包壳管,耐高温水蒸气氧化性能、耐磨性明显增强,是最具应用潜力的ATF包壳材料方案。因此,锆合金管表面Cr涂层的制备及性能考核成为近年来各国核材料领域科研工作者和核电企业的关注重点。为确保涂层的防护性,获得组织致密且粘附性好的Cr涂层技术成为关键。本文采用一种专门为长管材样品镀膜(样品长度可达1.2 m)而设计的磁控溅射设备,在锆合金管表面制备厚度为10~15μm的Cr涂层,采用SEM和XRD对涂层微观组织结构进行分析,并进行高温水蒸气氧化试验测试其防护性。本文旨在研究不同溅射参数对膜层微观结构及其防护性的影响,为全尺寸锆合金包壳管的Cr涂层制备技术开发提供参考。

【Abstract】 Chromium coating Zr-based cladding became the most advanced and mature solution for ATF fuel rod due to the enhanced wear resistance and the corrosion resistance in high temperature steam.The preparation and performance evaluation of Cr coating on zirconium alloy tubes have attracted much attention from both researchers and companies of nuclear power in the last few years.It is critical to obtain dense Cr layer with fine adhesion to the surface of Zr-based cladding to maximize the protection effect of Cr coating.In present work,a special magnetron sputtering equipment for long pipe sample coating are applied to prepare Cr coating with thickness of 10 μm to15 on zirconium alloy tubes.The microstructures of coating are characterized by SEM and XRD.The high temperature steam oxidation test was also carried out to evaluate the protective effect of Cr coating on Zr alloy.This work aims to study the influence of sputtering parameters on the microstructure and the protective effect of the coating,which provide a reference for the development of preparation technology of Cr coating on full-length cladding tubes.

  • 【会议录名称】 中国核科学技术进展报告(第六卷)——中国核学会2019年学术年会论文集第5册(核材料分卷、锕系物理与化学分卷、同位素分卷、核化学与放射化学分卷)
  • 【会议名称】中国核学会2019年学术年会
  • 【会议时间】2019-08-20
  • 【会议地点】中国内蒙古包头
  • 【分类号】TG174.4;TM623
  • 【主办单位】中国核学会
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