|About this Abstract
||Materials Science & Technology 2019
||Materials for Nuclear Applications
||Steam Oxidation and Microstructural Characterization of U3Si2 alloyed with Al, Cr, Nb, Y, and Zr
||Elizabeth S. Sooby, Cole Moczygemba, Geronimo Robles, Christopher Grote, Lu Cai, Peng Xu, Edward Lahoda
|On-Site Speaker (Planned)
||Elizabeth S. Sooby
Uranium silicides have proven of interest as advanced technology reactor fuels due to their enhanced thermal conductivity and high uranium density (U3Si and U3Si2) compared to traditional UO2. However, susceptibility to oxidation and wash out, 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. In support of the work presented, U3Si2 was alloyed with Al, Cr, Y, Nb, and Zr, ranging from 2-12 volume percent, using the arc melting method. Reported are thermogravimetric data for these alloyed compositions exposed to high temperature (300≤T≤ 1000°C) oxygen and steam alongside screening data for unalloyed U3Si2 and UO2. The microstructural degradation will be presented, and the modified reaction kinetics for the alloyed compositions will be assessed and impact to deployment in water cooler reactor systems discussed.