|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Modeling Stoichiometry Controlled Defect Dependent Densification in UO2±X
||Brandon Battas, Michael Cooper, Michael Tonks
|On-Site Speaker (Planned)
Many common nuclear fuels are processed from powders, and as such retain significant porosity. Therefore, it is important to understand how the fuel will sinter in a reactor setting, especially as that happens concurrent to other in reactor microstructural evolution. One aspect that affects the densification of sintered ceramic fuels, such as UO2±X, is the defect concentration. The defect concentration in the material helps determine the diffusivity, and the densification is largely diffusion controlled. This study focuses on mesoscale modeling of the effect of varying defect concentration in UO2±X, which is largely controlled by factors such as the stoichiometry of the fuel or the addition of irradiation to a system, on densification. We used atomistic simulations to quantify the impact of stoichiometry on defect concentrations, then used that data to model the densification in mesoscale using MARMOT.
||Computational Materials Science & Engineering, Modeling and Simulation, Nuclear Materials