|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Extended Defect Coalescence in Kr Irradiated UO2 During High Temperature Annealing
||Joshua Ferrigno, Chang-Yu Hung, Lingfeng He, Marat Khafizov
|On-Site Speaker (Planned)
Transmission electron microscopy (TEM) taken of 0.7 MeV-Kr irradiated UO2, after isochronal annealing (1000°C-1600°C, 1 hour) showed reduction in density and increase in size of interstitial dislocation loops and fission gas bubbles at increasing temperatures. A Rate theory (RT) model accounting for point defect recombination and absorption in loops and bubbles, and extended defect merging was employed to explore the significance of extended defect merging in UO2. Two primary mechanisms were considered for extended defect growth, the first looks at the interactions of the point defect populations with extended defects while the second examines solely the interaction of extended defects merging with another. Comparison of the models yielded the activation energy and confirmed that little interaction takes place with the point defect population during annealing due to the predomination of defect merging. This suggests that traditional Rate Theory models require consideration of separate defect mechanisms during annealing, not considered during irradiation.
||Characterization, Nuclear Materials, High-Temperature Materials