Zr/ZrC陶瓷涂层界面辐照损伤行为研究

As a core problem in the development of new gerneration of Zr-alloy ceramic coating fuel claddings, the interface between zirconium and ceramic coating plays a critical role in the high temperature corrosion resistance, radiation resistance, especially for the accident tolerance of new Zr-alloy ceramic coating claddings. Considered as one of the most potential accident-tolerant ceramic coatings to be applied for Zr-alloy cladding, the irradiation damage behavior of the Zr/ZrC ceramic interface were investigated in this proposal, which including (i) the prediction on irradiated defects evolution by ab initio method, (ii) experimental verification of the irradiation damage effects on the Zr/ZrC ceramic interface. The aim of this proposal is insight into the evolution behavior of irradiated defects, including vacancies and H/He interstitial, at Zr/ZrC interface and its effects on the interfacial bonding properties. These original results lay a solid foundation for the scientific design, optimized manufacture and property prediction of the new Zr alloy ceramic coating cladings.

界面是新一代锆合金陶瓷涂层核燃料包壳材料研究中的核心问题，新型锆合金陶瓷涂层包壳材料的耐高温腐蚀、抗辐照，特别是失水事故工况下的容忍性强烈依赖于锆合金基体与陶瓷涂层界面的结构稳定性及界面结合性能。本项目以Zr/ZrC陶瓷涂层材料为研究对象，围绕Zr/ZrC陶瓷涂层界面辐照损伤行为，开展：（i）Zr/ZrC陶瓷涂层界面辐照缺陷演变行为模拟研究；（ii）Zr/ZrC陶瓷涂层界面辐照损伤实验验证研究。项目拟从理论模拟和实验验证两方面来认识Zr/ZrC陶瓷涂层材料中辐照缺陷（空位、H/He间隙原子）演变行为，掌握辐照缺陷对Zr/ZrC陶瓷涂层界面结构稳定性、界面结合性能的影响规律，揭示Zr/ZrC陶瓷涂层界面辐照损伤机理，为新型锆合金陶瓷涂层包壳材料的结构设计、工艺优化以及性能预测提供重要参考依据。

界面是新一代锆合金陶瓷涂层核燃料包壳材料研究中的核心问题，新型锆合金陶瓷涂层包壳材料的耐高温腐蚀、抗辐照，特别是失水事故工况下的容忍性强烈依赖于锆合金基体与陶瓷涂层界面的结构稳定性及界面结合性能。项目以Zr/ZrC陶瓷涂层材料为研究对象，围绕Zr/Z rC陶瓷涂层界面辐照损伤行为开展理论计算和实验验证研究。项目研究揭示了ZrC陶瓷涂层体相、以及Zr/ZrC界面的辐照缺陷（空位、H、He）结构稳定性、扩散行为；评估了缺陷对涂层结构稳定性、界面结合性质的影响规律，并从电子/原子层次揭示了其影响机理。研究结果在Applied Surface Science、Journal of Nuclear Materials等期刊发表论文5篇。项目研究成果将为新型锆合金陶瓷涂层包壳材料的结构设计、工艺优化以及性能预测提供重要参考依据。