Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction
This work characterizes the crystallographic evolution of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) while cooling from equilibration, single phase ?-U-Zr, at 900 °C to ambient temperature using time-of-flight neutron diffraction. The ß-U phase was unobserved during cooling at 1 °C/min in all alloys. All alloys followed the phase transformation pathway of […]
Computational determination of a primary diffusion mode in gamma U-10Mo under irradiation
Low enriched uranium (< 20 % 235U)-molybdenum (U-Mo) monolithic fuel is the primary candidate for high performance research and test reactors, and is in the process of being qualified to replace highly enriched uranium (= 20 % 235U) fuel. As part of the qualification process, it is critical to understand and predict the behavior of […]
Microstructural-Level Fuel Performance Modeling of U Mo Monolithic Fuel
As the physics that governs the microstructural evolution of nuclear fuel span various time and spatial scales, to fully understand the fuel behavior inevitably involves atomic to mesoscale resolution that can be difficult to determine experimentally. Microstructural-level modeling and simulations can be used to develop physics-based materials models that can provide physical understanding to inform […]