Uranium silicides are considered for advanced technology reactor fuels due to their enhanced thermal conductivity and high uranium density (U₃Si and U₃Si₂) compared to traditional UO₂. Susceptibility to oxidation and wash out, in the event of a cladding breech, could limit the potential for deployment of silicides as accident tolerant fuels. Mitigating the water reaction for U₃Si₂ could enable its use as an accident tolerant, high uranium density fuel or as a composite fuel constituent. Reported here is the impact of alloying additions of Al, Cr and Y on the high temperature, steam oxidation response of U₃Si₂. In addition to the thermogravimetric response, as melted microstructures, phase compositions and post oxidation analysis are also presented. The investigation shows steam oxidation dynamics are altered, from non-alloyed U₃Si₂, under thermally ramped conditions. However, additional alloy development of these fuel forms is necessary for further consideration as candidate accident tolerant fuels in water-cooled reactor designs.

与传统的UO ₂相比，铀硅化物由于具有更高的导热性和较高的铀密度（U ₃ Si和U ₃ Si ₂）而被认为是先进技术反应堆燃料。如果发生覆盖层后膛，容易受到氧化和冲刷，这可能会限制部署硅化物作为耐事故燃料的潜力。减轻U ₃ Si ₂的水反应可使其用作耐事故的高铀密度燃料或复合燃料成分。这里报道的是Al，Cr和Y合金化添加对U ₃ Si _2的高温蒸汽氧化反应的影响。除了热重量反应外，还介绍了熔融的微结构，相组成和后氧化分析。研究表明，在热升温条件下，非合金U ₃ Si _2的蒸汽氧化动力学发生了变化。但是，需要进一步开发这些燃料形式的合金，以便进一步考虑作为水冷反应堆设计中的候选耐事故燃料。