Cr涂层锆合金耐事故燃料包壳材料高温蒸汽氧化行为研究进展

Research Progress on High-Temperature Steam Oxidation Behavior of Cr-Coated Zirconium Alloy as Accident-Tolerant Fuel Cladding

摘要:

耐事故核燃料能显著增强轻水核反应堆在失水事故下抵御堆芯熔化的能力,是核燃料技术变革和核电安全技术提升的重要方向。在现役锆合金包壳表面涂覆Cr涂层,形成具备良好结合力、优异耐高温高压水腐蚀性能和抗高温氧化性能的新型包壳材料,是最有望在短期内获得实际工程应用的耐事故核燃料解决方案。本文综述了Cr涂层锆合金在高温蒸汽环境中氧化行为研究进展,重点关注Cr涂层的氧化动力学、Cr涂层微观组织对抗氧化性能的影响,以及长时间氧化后Cr涂层的失效机理和Cr-Zr互扩散行为。此外,总结了增强Cr涂层抗氧化性能和抑制Cr-Zr互扩散的策略,并展望了未来的发展方向,以期为Cr涂层核燃料包壳的优化设计和工程应用提供参考。

Abstract:

Accident-tolerant fuel can significantly enhance the capability of light-water nuclear reactors to withstand core melting under LOCA, is a revolutionary development of nuclear fuel technology and nuclear power safety. Cr-coating deposited on the current Zr-based nuclear fuel cladding demonstrates good adhesion, excellent corrosion resistance in high-temperature and high pressure water, and high-temperature oxidation resistance. Therefore, Cr-coated zirconium alloys emerge as the most promising ATF solution for practical engineering application in nearest future. The present paper reviews the research progress on oxidation behavior of Cr-coated zirconium alloy in high-temperature steam environment. The oxidation kinetics of the Cr coating, the effect of microstructure on the anti-oxidation performance of the Cr coating, the failure mechanism of the Cr coating after long-term oxidation and the Cr-Zr interdiffusion behavior are discussed. Additionally, strategies for enhancing the anti-oxidation performance of the Cr coating and suppressing Cr-Zr interdiffusion are summarized, and future development directions are prospected, aiming to provide references for the optimization design and engineering application of Cr-coated Zr-based nuclear fuel cladding.