400℃下5mev质子辐照Zr合金表面生长、内部缺陷及界面混合

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Huan Chen , Changyong Zhan , Wenjuan Gong , Peinan Du , Ruiqian Zhang , Jijun Yang , Yu Wang , Tianguo Wei , Hongyan Yang , Yu Zou , Baoqin Fu
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引用次数: 0

摘要

采用XRD、SEM、TEM和纳米压痕等方法对5 MeV质子辐照后Cr涂层的表面、内部和界面损伤进行了表征。辐照后,由于扩散的Cr原子的分离和再沉积,在表面形成具有细化晶粒的Cr7C3生长层。辐照引起的Cr涂层缺陷主要有空洞、位错和气泡-空位复合物。重要的是,发现了电弧离子镀铬涂层的辐照软化,这应该是由于固有沉降和辐照缺陷的变形恢复和重组。在涂层-衬底界面,发现了ZrCr2 C14相、多层界面和优先扩散,这意味着链状或层状Cr原子可能主导界面扩散。在机理上,分析了辐照缺陷的形成机理,并采用辐照增强扩散、弹道碰撞和锐化效应来解释界面混合。在Cr通量方程中提出了各向异性扩散的相关系数,用于解释(110)主导型扩散。结果表明,涂层的辐照效果取决于涂层制备过程中产生的固有缺陷和择优取向。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Surface growth, inner defects and interface mixing of Cr coating on Zr alloy irradiated by 5 MeV protons at 400°C

Surface, inner and interface damages of Cr coatings irradiated by 5 MeV protons were characterized by XRD, SEM, TEM and nanoindentation in this work. After irradiation, a Cr7C3 growth layer with refined grains was formed on the surface due to the separation and redeposition of diffused Cr atoms. Irradiation-induced defects in the Cr coatings were voids, dislocations, and bubble-vacancies complexes. Importantly, irradiation softening was found for the arc-ion plated Cr coating, which should be due to the deformation recovery and recombination of inherent sinks and irradiation defects. At the coating-substrate interface, the ZrCr2 C14 phase, a multilayered interface and the preferential diffusion were found, meaning chained or layered Cr atoms may dominate the interface diffusion. In mechanism, formation mechanisms of irradiation defects are analyzed and the irradiation-enhanced diffusion, ballistic collision and the sharpening effect are employed to explain the interface mixing. A correlation coefficient of the anisotropic diffusion is proposed in the Cr flux equation for explaining the (110)-dominated diffusion. The results show that irradiation effects of coatings depend on the inherent defects and preferred orientation produced in the preparation process of coatings.

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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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