Irradiation behavior of atomized U-10wt./100 Mo alloy aluminum matrix dispersion fuel meat at low temperature

摘要

In order to examine the in-reactor behavior of very-high-density dispersion fuels for high flux performance research reactors, U-10wt./100 Mo alloy dispersions in an aluminum matrix heave been irradiated at low temperature in the Advanced Test Reactor (ATR). The alloy fuel dispersant was produced by a centrifugal atomization process. The fuel Shows stable in-reactor irradiation behavior to a fission density of 5×10~27 m~-3 at an irradiation temperature of ～65 deg. C. The fuel-matrix interaction layer growth rate is similar to that observed in uranium-silicide fuels.