利用热反射技术评估用于耐事故燃料的铬涂层的导热性能

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Yuzhou Wang, Yaoyang Zhang, Hailin Zhai, Jishen Jiang, Yibo Zhang, Qiang Zhang, Xianfeng Ma
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引用次数: 0

摘要

要在核反应堆内使用铬涂层作为事故耐受燃料包壳,就必须全面了解其性能,包括机械、化学、辐照和热性能。虽然对前者进行了大量研究,但对决定燃料温度和影响燃料安全的铬涂层热传导特性的研究相对不足。本研究采用高分辨率频率和空间域热反射技术,对通过多弧离子镀制造的 12 微米厚铬涂层的热传导性进行了研究。真空退火用于控制涂层的形态,以探索晶粒尺寸的影响。结果表明,尽管沉积涂层和退火涂层具有不同的晶粒形态,但其热传导率与块状涂层相似。随着临界尺寸减小到 0.5 μm 以下,边界对热传导的影响预计会变得更加突出。未来还需要进行研究,以解决不利反应(如氧气进入和辐照)对铬涂层热性能的潜在影响,从而确保在核反应堆环境中安全高效地运行。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Evaluation of the thermal conductivity of chromium coatings for accident tolerant fuels using thermoreflectance techniques
The deployment of Cr coatings as accident tolerant fuel cladding inside nuclear reactors necessitates a thorough understanding of their performance, including mechanical, chemical, irradiation, and thermal properties. While significant research has delved into the former, the thermal transport properties of Cr coatings, which dictates fuel temperature and impacts fuel safety, have been relatively underexplored. This work presents an investigation into the thermal conductivity of 12 µm-thick Cr coatings fabricated by multi-arc ion plating employing high-resolution frequency and spatial domain thermoreflectance techniques. Vacuum annealing was utilized to control the morphology of coatings to explore the impact of grain size. The results indicate that both as-deposited and annealed coatings, despite possessing distinct grain morphologies, exhibit thermal conductivities similar to their bulk counterparts. The influence of boundaries on thermal transport is anticipated to become prominent as the critical dimension diminishes below 0.5 μm. Future investigation is required to address the potential impact of adverse reactions, such as oxygen ingress and irradiation, on the thermal properties of Cr coatings to ensure safe and efficient operation in nuclear reactor environments.
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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