|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors VII
||Advanced Characterization of Irradiated UO2 Fuel
||Lingfeng He, David Shuh, Xianming Bai, Michael Moorehead, Brandon Miller, Claude Degueldre, Jason Harp
|On-Site Speaker (Planned)
Fine microstructure at both the center and edge regions of UO2 fuel irradiated at Belgian Reactor 3 (BR3) has been characterized using atomic-resolution scanning transmission electron microscope (STEM) with super-X energy dispersive spectroscopy (EDS) system at Irradiated Materials Characterization Laboratory (IMCL) at Idaho National Laboratory (INL) as well as scanning transmission X-ray microscopy (STXM) at Lawrence Berkeley National Laboratory (LBNL). The detailed microstructure and composition of solid fission products, five-metal (Ru-Mo-Pd-Tc-Rh) precipitates, and their orientation relationship with UO2 matrix have been determined. Fission gas bubble size, density, gas content and bubble pressure have been measured and calculated. The nucleation and growth mechanisms of fission products as well as the formation of high burnup structure (HBS) will be discussed.
||Planned: Supplemental Proceedings volume