提高Zr合金包层微动磨损性能的CrTiSiN超晶格涂层方法

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-08-15 DOI:10.1016/j.jnucmat.2025.156107

Jianqiao Yang , Lifeng Yang , Yanguang Cui , Zhuoyu Zhang , Xunyang Ke , Fen Zhao , Xintao Zhang , Yufan Jiang , Xianglong Guo , Junqiang Lu , Di Yun

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引用次数: 0

摘要

在本研究中，使用实验室规模的蒸压罐微动装置研究了包覆CrN/TiSiN多层结构的Zr合金的微动磨损行为。多层涂层呈现出由CrN和Ti2N单元组成的超晶格结构，每层厚度约为50 nm。与未涂覆的Zr合金相比，CrTiSiN涂层的耐磨性显著提高。CrTiSiN涂层的最大磨损损失为36%，残余CrTiSiN涂层未观察到明显的裂纹。当摩擦氧化锆微窝时，涂层试样的磨损体积和最大磨损深度分别比未涂层的试样低约21倍和7.1倍。在磨损表面观察到由含Zr、Cr、Ti和O的磨损碎屑组成的摩擦学诱导三体层。CrTiSiN涂层的主要磨损机制为黏着磨损，磨料磨损占次要作用。

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Enhancing the fretting wear resistance of Zr alloy claddings: A CrTiSiN superlattice coating approach

In this study, the fretting wear behavior of a Zr alloy coated with a CrN/TiSiN multilayer structure was investigated using a lab-scale autoclave fretting apparatus. The multilayer coating exhibited a superlattice architecture consisting of CrN and Ti₂N units, with each individual layer having a thickness of approximately 50 nm. The CrTiSiN coating demonstrated significantly improved wear resistance compared to the uncoated Zr alloy. The maximum wear loss of the CrTiSiN coating is 36 %, and no visible cracks were observed in the residual CrTiSiN coating. When fretted against a Zirlo dimple, the wear volume and maximum wear depth of the CrTiSiN coated sample were approximately 21 times and 7.1 times lower than those of the uncoated Zirlo specimen. A tribologically induced three-body layer, composed of wear debris containing Zr, Cr, Ti, and O, was observed on the worn surface. The dominant wear mechanism of the CrTiSiN coating was identified as adhesive wear, with a minor contribution from abrasive wear.

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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.