|About this Abstract
||2020 TMS Annual Meeting & Exhibition
||Accelerated Materials Evaluation for Nuclear Applications Utilizing Irradiation and Integrated Modeling
||Comparison of Radial Microstructural Changes in Fast Reactor MOX Fuels Across Varying Burnup Profiles
||Riley Parrish, Assel Aitkaliyeva
|On-Site Speaker (Planned)
This work will show results from the examination of three fast reactor mixed-oxide (MOX) fuel pellets irradiated to approximately 3%, 14%, and 21% fissions per initial metal atom (FIMA) in the Fast Flux Test Facility. Results from scanning electron microscopy (SEM) and energy dispersive X-ray spectroscopy (EDS) analysis will demonstrate the evolution of microstructural features along the radial thermal gradient of the fuel pellet. Across all burnups, the morphology and distribution of solid fission products show distinct differences at each of the radial positions. At 14% and 21% FIMA, a Pd-rich metallic precipitate begins to form alongside the five metal ε-phase particles and insoluble perovskite oxide. The fuel-cladding gap has accumulated metallic species on the cladding surface along with a dense layer rich in volatile fission products consistent with the Joint Oxide Gain.