Mechanical and high-temperature steam oxidation properties of Cr coatings deposited via high-power impulse magnetron sputtering

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2024-10-24 DOI:10.1016/j.jnucmat.2024.155482

Ding Chen , Wei Dai , Daoxuan Liang , Qimin Wang , Jun Yan

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Abstract

Applying protective coatings to Zr alloy cladding surfaces is one of the better methods to design fuel tolerant materials. In this study, the surface of a Zr-4 alloy was coated with Cr using high-power impulse magnetron sputtering. Furthermore, the mechanisms by which bias voltages affect the mechanical characteristics, resistance to high-temperature steam oxidation, and coating structure were elucidated. The coating exhibits a strong (200) weave structure with coarse grains at a bias voltage of -100 V. With increasing bias, the energy of deposited particles increases, grains continue to grow, (200) preferential growth orientation disappears, and the coating exhibits a (110) crystal orientation. The growth structure of the coating first shows a tendency to be dense and then loose. For the Cr coating with a (200) crystal orientation, a dense oxide layer is preferentially formed after oxidation, which can effectively block the internal diffusion of O. With increasing oxidation time, coarse Cr grains can effectively block the external diffusion of Zr. Furthermore, the Cr coating exhibiting a (110) crystal orientation was severely oxidized after oxidation, resulting in the formation of cracks at the film base; this accelerated the outward diffusion of Zr.

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通过高功率脉冲磁控溅射沉积的铬涂层的机械和高温蒸汽氧化特性

在 Zr 合金包层表面涂覆保护层是设计耐燃料材料的较好方法之一。在这项研究中，利用高功率脉冲磁控溅射技术在 Zr-4 合金表面镀上了铬。此外，还阐明了偏压对机械特性、抗高温蒸汽氧化性和涂层结构的影响机制。随着偏压的增加，沉积粒子的能量增加，晶粒继续生长，（200）优先生长取向消失，涂层呈现出（110）晶体取向。涂层的生长结构呈现先致密后疏松的趋势。对于晶体取向为（200）的铬镀层，氧化后会优先形成致密的氧化层，这可以有效阻止 O 的内部扩散；随着氧化时间的延长，粗大的铬晶粒可以有效阻止 Zr 的外部扩散。此外，呈现（110）晶体取向的铬涂层在氧化后被严重氧化，导致膜基形成裂缝；这加速了 Zr 的向外扩散。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

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.