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Surface Modification Techniques for Increased Corrosion Tolerance of Zirconium Fuel Cladding

机译:表面改性技术以提高锆燃料熔覆层的耐腐蚀性

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摘要

Corrosion is a major issue in applications involving materials in normal and severe environments, especially when it involves corrosive fluids, high temperatures, and radiation. Left unaddressed, corrosion can lead to catastrophic failures, resulting in economic and environmental liabilities. In nuclear applications, where metals and alloys, such as steel and zirconium, are extensively em- ployed inside and outside of the nuclear reactor, corrosion accelerated by high temperatures, neu- tron radiation, and corrosive atmospheres, corrosion becomes even more concerning. The objec- tives of this research are to study and develop surface modification techniques to protect zirconium cladding by the incorporation of a specific barrier coating, and to understand the issues related to the compatibility of the coatings examined in this work. The final goal of this study is to recommend a coating and process that can be scaled-up for the consideration of manufacturing and economic limits.This dissertation study builds on previous accident tolerant fuel cladding research, but is unique in that advanced corrosion methods are tested and considerations for implementation by industry are practiced and discussed. This work will introduce unique studies involving the materials and methods for accident tolerant fuel cladding research by developing, demonstrating, and consid- ering materials and processes for modifying the surface of zircaloy fuel cladding. This innova- tive research suggests that improvements in the technique to modify the surface of zirconium fuel cladding are likely.Three elements selected for the investigation of their compatibility on zircaloy fuel cladding are aluminum, silicon, and chromium. These materials are also currently being investigated at other labs as alternate alloys and coatings for accident tolerant fuel cladding. This dissertation also investigates the compatibility of these three elements as surface modifiers, by comparing their mi- crostructural and mechanical properties. To test their application for use in corrosive atmospheres, the corrosion behaviors are also compared in steam, water, and boric-acid environments. Various methods of surface modification were attempted in this investigation, including dip coating, diffu- sion bonding, casting, sputtering, and evaporation. The benefits and drawbacks of each method are discussed with respect to manufacturing and economic limits. Characterization techniques utilized in this work include optical microscopy, scanning electron microscopy, energy-dispersive spec- troscopy, X-ray diffraction, nanoindentation, adhesion testing, and atomic force microscopy. The composition, microstructure, hardness, modulus, and coating adhesion were studied to provide en- compassing properties to determine suitable comparisons and to choose an ideal method to scale to industrial applications. The experiments, results, and detailed discussions are presented in the following chapters of this dissertation research.
机译:在涉及正常和严酷环境中的材料的应用中,腐蚀是一个主要问题,尤其是当涉及腐蚀性流体,高温和辐射时。如果不加以解决,腐蚀会导致灾难性故障,从而造成经济和环境责任。在核反应堆的内部和外部广泛使用金属和合金(例如钢和锆)的核应用中,高温,中子辐射和腐蚀性气氛会加速腐蚀,腐蚀变得更加重要。这项研究的目的是研究和开发表面改性技术,以通过掺入特定的阻隔涂层来保护锆覆层,并了解与这项工作中检验的涂层的相容性有关的问题。这项研究的最终目的是推荐一种可以扩大规模的涂层和工艺,以考虑制造和经济方面的限制。本论文的研究建立在以前的耐事故性燃料包壳研究的基础上,但其独特之处在于对先进的腐蚀方法进行了测试实践并讨论了按行业实施的注意事项。这项工作将通过开发,演示和考虑用于改性锆合金燃料包壳表面的材料和工艺,来介绍涉及耐事故燃料包壳研究的材料和方法的独特研究。这项创新研究表明,可能会对改进锆燃料包壳表面的技术进行改进。为研究其在锆合金燃料包壳中的兼容性而选择的三个元素是铝,硅和铬。这些材料目前也在其他实验室进行研究,以用作耐事故燃料包壳的替代合金和涂层。本文还通过比较它们的微观结构和力学性能,研究了这三种元素作为表面改性剂的相容性。为了测试其在腐蚀性气氛中的应用,还比较了在蒸汽,水和硼酸环境中的腐蚀行为。在这项研究中尝试了多种表面改性方法,包括浸涂,扩散结合,浇铸,溅射和蒸发。关于制造和经济限制,讨论了每种方法的优缺点。在这项工作中使用的表征技术包括光学显微镜,扫描电子显微镜,能量分散光谱,X射线衍射,纳米压痕,附着力测试和原子力显微镜。对组成,微观结构,硬度,模量和涂层附着力进行了研究,以提供包罗万象的性能,以确定合适的比较方法,并选择一种理想的方法以适合工业应用。本论文研究的以下各章对实验,结果和详细讨论进行了介绍。

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    Carr James;

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  • 年度 2016
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