众所周知，γ-相U-Mo合金是RERTR计划中最有潜力的快堆和实验堆燃料，在辐照条件下，级联碰撞会在燃料内部产生大量缺陷，缺陷的演化导致燃料的微观结构发生改变，燃料的力学性能对其微观结构有很强的依赖性，由辐照损伤引起的力学性能的退化可进一步导致燃料失效，因此，认识辐照损伤对U-Mo合金力学性能的影响对燃料的安全设计具有重要意义。. 目前，关于辐照后U-Mo合金力学性能的数据鲜有报道，鉴于此，本项目拟采用分子动力学研究辐照损伤对U-Mo合金力学性能的影响，研究内容包括U-Mo合金中的级联碰撞、辐照缺陷的演化过程、通过拉伸模拟研究辐照缺陷对U-Mo合金力学性能和变形机制的影响。本项目将在原子尺度上探明辐照损伤对U-Mo合金力学行为的影响结果和影响机理，为提高快堆和实验堆燃料的安全性和抗辐照能力提供帮助。

It is well-known that U-Mo alloy in γ-phase state is the most possible fuels for future fast and research reactors in the frame of RERTR program. Under irradiation condition, displacement cascades lead to numerous radiation defects. Radiation damage will change the microstructure of fuel, and the mechanical properties of nuclear fuel depend significantly on the evolution of the material microstructure..The degeneration of mechanical properties may result in fuel failure. So, understanding the radiation damage effects on the mechanical behavior of fuel is important for safe fuel design.. So far the studies of post-irradiation mechanical behavior of U-Mo alloy are extremely limited, so we will study the effects of radiation damage on mechanical behavior of U-Mo alloy employing molecular dynamics simulations. The investigation includes the simulation of displacement cascades and the evolution of radiation defects in U-Mo alloy, the mechanical properties and deformation behavior will also be investigated through tensile simulations. The results will give a detailed atomistic understanding of the interaction between irradiation damage and mechanical behavior of U-Mo fuel. Our investigation will be helpful to improving irradiation stability and life of the fuel in future fast and research reactors