Xiaodong He , Yu Jin , Zijin Liu , Xiaoze Yue , Guangan Zhang , Shunhua Wang , Lunlin Shang
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引用次数: 0
摘要
根据 ATF 设计理念,在压水堆事故中,铬基涂层是最有前途的锆合金包壳保护涂层。然而,影响铬涂层抗氧化性的主要因素是铬和锆的相互扩散。在这项研究中,使用闭场不平衡磁控溅射技术在锆合金表面沉积了带有 Nb、Mo 和 Ta 三种难熔金属夹层的铬涂层。研究考察了不同中间膜对 1200 ℃ 蒸汽条件下铬镀层的微观结构、氧化性能和界面演化过程的影响,并与不含中间膜的铬镀层进行了比较。结果表明,难熔金属中间层会影响铬镀层晶粒的取向和生长速度。氧化过程中在中间层中形成的拉维斯相混合层有效地阻碍了 O 和 Cr 向锆合金基体的扩散,增强了锆合金的抗氧化性。此外,Mo 和 Ta 元素向 Zr 层的扩散速度和空位浓度都超过了向 Cr 层的扩散速度和空位浓度。在冷却过程中,Zr-4 基体中形成沉淀相,而 Nb 涂层则在β-Zr 中形成无限固溶体。
Effect of diffusion barriers on steam oxidation properties and interface evolutions of Cr coating for zirconium alloy at 1200 °C
Under the ATF design concept, Cr-based coating is the most promising zirconium alloy cladding protective coating in the case of PWR accidents. However, the primary factor affecting the oxidation resistance of Cr coatings is the interdiffusion of Cr and Zr. In this study, Cr coatings with three refractory metal interlayers of Nb, Mo, and Ta were deposited on zirconium alloy surfaces using closed-field unbalanced magnetron sputtering. The study investigated the effects of different interlayers on the microstructure, oxidation properties, and interface evolution process of Cr coatings under steam conditions at 1200 ℃, and compared them with Cr coatings without intermediate layers. The results indicate that the refractory metal interlayer influences the orientation and growth rate of Cr coating grains. The formation of a Laves phase mixed layer in the interlayer during oxidation effectively hinders the diffusion of O and Cr to the zirconium alloy matrix, enhancing its oxidation resistance. Furthermore, the diffusion rate and vacancy concentration of Mo and Ta elements to the Zr layer exceed that of diffusion to the Cr layer. During the cooling process, a precipitate phase forms in the Zr-4 matrix, while the Nb coating forms an infinite solid solution in the β-Zr.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.