|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Computational Materials Engineering for Nuclear Reactor Applications
||Z-7: Gas Bubble Kinetics in an Irradiated U-Mo Using a Multistate Simulation Approach
||Linyun Liang, Zhi-Gang Mei, Mihai Anitescu, Abdellatif M. Yacout, Yeon Soo Kim
|On-Site Speaker (Planned)
Computer simulation as a cost-effective method can provide promising opportunities in understanding and predicting the irradiation induced microstructural damage in nuclear materials. In this talk, a multi-scale simulation approach is used to study the gas bubble evolution kinetics in irradiated U-Mo alloy fuels. Density functional theory is utilized to predict the defect formation energies, the Xe-U-Mo interfacial energy, and the elastic constants of U-Mo alloys, among other quantities. These obtained material properties are then incorporated into a mesoscale model to study the kinetics of gas bubbles in U-Mo under irradiation. By developing a new free energy model of Xe gas bubble based on the van der Waals equation of state, the gas bubble pressure can be estimated. We systematically investigate the effect of Xe, vacancy, and SIA concentration, fission defect generation and their recombination, sink strength, grain boundaries, and elastic interaction on the growth kinetics of gas bubbles.
||Planned: A print-only volume