基于实验和第一性原理的CrSi包覆Zr合金扩散和溶解机理

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Pengfei Ma , Shihao Wu , Bo Liu , Haoli Wang , Yaping Zhang , Yicong Lan , Dayan Ma , Junkai Deng , Yapei Zhang , Kui Ge , Wenxi Tian , Suizheng Qiu , G.H. Su
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引用次数: 0

摘要

耐事故燃料(ATF)是提高核反应堆安全性的一个重要研究方向,而cr包覆锆合金包层是耐事故燃料包层的主要候选材料之一。然而,在超设计基础事故(BDBA)和反应性引发事故(RIA)条件下,Cr-Zr共晶熔化对包层的完整性和安全性提出了重大挑战。目前的研究表明,抑制Cr/Zr界面元素扩散是设计Cr涂层抗共晶熔化能力增强的关键,而最有效的方法是在涂层和基体之间引入扩散阻挡层。在本研究中,采用实验和第一性原理模拟相结合的方法研究了CrSi涂层中的原子扩散行为和溶解机制。采用多弧离子束物理气相沉积系统制备CrSi涂层,随后在19世纪进行真空退火,以检查CrSi涂层与锆衬底之间的界面扩散现象。同时进行了划伤试验和蒸汽氧化试验,考察了CrSi涂层的性能。此外,通过第一性原理计算建立了CrSi涂层与锆基体的界面溶解模型,阐明了Cr和Si原子在HCP-Zr和转化BCC-Zr相中的溶解机理。本研究为开发先进的含cr - si涂层提供了新的见解和理论基础,促进了BDBA和RIA条件下涂层锆包层的工程应用。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

Diffusion and dissolution mechanism of CrSi coated Zr alloy by experiments and first principles

Diffusion and dissolution mechanism of CrSi coated Zr alloy by experiments and first principles
Accident-tolerant fuel (ATF) represents a critical research direction for enhancing nuclear reactor safety, with Cr-coated zirconium alloy cladding being one of the leading ATF cladding candidates. However, under beyond-design-basis accidents (BDBA) and reactivity-initiated accident (RIA) conditions, the eutectic melting of Cr-Zr poses a significant challenge to cladding integrity and safety. Current research suggests that suppressing elemental diffusion at the Cr/Zr interface is key to designing Cr coatings with enhanced resistance to eutectic melting, with the most effective approach being the introduction of a diffusion barrier layer between the coating and the substrate. In this study, a combined experimental and first-principles simulation approach was employed to investigate atomic diffusion behavior and dissolution mechanisms in CrSi coatings. CrSi coatings were conducted using a multi-arc ion beam physical vapor deposition system, followed by vacuum annealing in the 1800s to examine interfacial diffusion phenomena between the CrSi coating and the zirconium substrate. Meanwhile, the scratch tests and steam oxidation experiments were performed to investigated the CrSi coating performance. Furthermore, first-principles calculations were further conducted to establish interfacial dissolution models for the CrSi coating and the zirconium substrate, elucidating the dissolution mechanisms of Cr and Si atoms in both the HCP-Zr and transformed BCC-Zr phases. This study provides novel insights and theoretical foundations for the development of advanced Cr-Si-containing coatings, facilitating the engineering application of coated zirconium cladding under BDBA and RIA conditions.
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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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