在聚变裂变混合堆概念设计中,铀钼合金除承担裂变放能的作用外,还需要作为结构材料,因此对其高温力学性能应予以关注。采用真空感应熔炼法制备了铸态U-10%Mo(质量分数)合金并进行了均匀化热处理,利用X射线衍射(XRD)、扫描电子显微镜(SEM)方法对其相结构和显微组织进行了分析,测试了样品在室温和400,500,600℃下的高温力学性能。实验发现,铸态U-10%Mo合金晶界处存在大量铀的碳化物和氧化物杂质聚集,这可能是其呈脆性沿晶断裂的原因所在。随着试验温度升高,合金的极限强度有所下降。 In the conceptual design of fusion fission hybrid reactor, uranium-molybdenum alloy needs to be used as structural material in addition to fission release energy, so attention should be paid to its high temperature mechanical properties. The as-cast U-10% Mo (mass fraction) alloy was prepared by vacuum induction melting and homogenized. The phase structure and microstructure were characterized by X-ray diffraction (XRD) and scanning electron microscopy (SEM) For analysis, the high temperature mechanical properties of the samples were tested at room temperature and at 400, 500 and 600 ℃. It is found that a large amount of uranium carbide and oxide impurities accumulate at grain boundaries of the as-cast U-10% Mo alloy, which may be the reason for the brittle intergranular fracture. As the test temperature increases, the ultimate strength of the alloy decreases.