| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
|
| Presentation Title |
Investigation of the Creep and Fracture Behavior of Irradiated UO2 Fuel Through Density Functional Theory (DFT) |
| Author(s) |
Maria Giamouridou, Huan Liu, Pär Olsson |
| On-Site Speaker (Planned) |
Maria Giamouridou |
| Abstract Scope |
Uranium dioxide (UO2) is the most commonly used advanced fuel in the nuclear industry. Despite its widespread use, there is a lack of information associated with the impact of irradiation on the creep and fracture behavior of the UO2 fuel. Understanding the interaction mechanisms between mobile dislocations as well as grain boundaries with irradiation defects, such as point defects, fission products, bubbles, and cavities is crucial. These interactions significantly affect the mechanical properties, including the creep behavior of the irradiated UO2. Through electronic structure calculations, particularly density functional theory (DFT), we investigate the atomic scale forces, simulating the behavior of the dislocations and grain boundaries under the presence of defects. The results of the simulations are discussed in detail, providing valuable insights into the dislocation behaviors associated with defects in irradiated UO2 and highlighting the importance of theoretical methods in understanding complex interactions. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Ceramics, Mechanical Properties, Modeling and Simulation |