本项目是为适应目前国际上发展第四代反应堆的趋势，虑及第四代反应堆燃料包壳材料所面临的科学挑战，并面向我国核电技术可持续发展的材料自主化需求而开展的基础研究。本项目拟利用高能离子加速器，在不同温度及辐照剂量的辐照条件下，对第四代反应堆燃料包壳候选材料氧化物弥散强化（ODS）钢进行辐照，并通过辐照前后的微观组织分析及在铅铋金属溶液中腐蚀行为的试验和理论分析，研究在铅铋金属溶液腐蚀前后辐照对ODS钢的影响规律和机理。通过本项目的研究，揭示辐照区域的化学成分、点缺陷、析出相等微观组织特征的影响规律，揭示辐照对ODS钢在铅铋金属溶液环境下腐蚀行为的影响规律及腐蚀机理，为第四代反应堆燃料包壳材料的研发提供技术数据支撑与基础科学成果储备。

This project is a basic research proposed by considering the international trend to develop the Generation-IV nuclear reactors, the challenge to the reactor fuel cladding materials and on the requirement for our independent nuclear technology for sustainable materials. The project will use high-energy ion accelerator irradiating on candidate material as oxide dispersion strengthened (ODS) steel in different temperatures and doses. By analyzing the microstructures before and after irradiation, and the corrosion behavior in liquid lead-bismuth eutectic, the key problems will be studied. That is what the mechanism and rules are for the ion irradiation on ODS steel in liquid lead-bismuth eutectic. From the study of this project, the rules for how the ion irradiation influence the microstructures of ODS steel's irradiated surface as chemical composition, point defects, precipitate phases and so on will be revealed. And the mechanisms for influence of irradiation on ODS steel in liquid lead-bismuth eutectic will also be revealed. This project will provide technical support and basic science achievement for the research and development of fuel cladding materials for Generation-IV nuclear reactors.