|About this Abstract
||2021 TMS Annual Meeting & Exhibition
||Ceramic Materials for Nuclear Energy Research and Applications
||Microstructural Analysis and Micro-mechanical Testing on Xenon-irradiated Uranium Dioxide
||Mack Cullison, Fei Teng, David Fraser, Boopathy Kombaiah, Kun Mo, Jie Lian, Tianyi Chen, Fabiola Cappia
|On-Site Speaker (Planned)
Spark plasma sintered UO2 with initial grain sizes of 10 and 70 µm were irradiated by 84 MeV Xenon ions up to about 1400 peak displacements per atom (dpa) at 350 to 500ºC. Ion-implantation is used to induce microstructure modifications that mimic in-reactor damage occurring at high burnup. Transmission electron microscope (TEM) characterization shows strong depth dependency in irradiated microstructure. 1-20 nanometer sized bubbles were observed near the peak dpa region while grain refinement was observed near the irradiated surface. Micro-mechanical testing will be applied to samples receiving different damage levels to determine the fracture behavior, strength, toughness and elastic local UO2 properties as a function of microstructural development under irradiation. Micromechanical properties in high-dpa irradiated UO2 will be useful for fuel development.
||Mechanical Properties, Characterization, Nuclear Materials