About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramics and Ceramic-Based Composites for Nuclear Applications III
|
| Presentation Title |
Multi-Phase Modeling of Defect Accumulation and Thermal Conductivity Degradation for Irradiated UO2 Fuel |
| Author(s) |
Mutaz Alshannaq, Marat Khafizov |
| On-Site Speaker (Planned) |
Mutaz Alshannaq |
| Abstract Scope |
Nuclear fuels operate under extreme conditions characterized by high temperatures and intense radiation fields that significantly affect their thermal properties. These conditions lead to the formation and evolution of both point and extended defects within the fuel material. A comprehensive study was conducted to track point defects and dislocation loop evolution throughout the fuel lifecycle, encompassing in-pile irradiation, out-pile irradiation, and annealing cycles, utilizing the Rate Theory (RT) Model. The Ronchi Model was utilized in parallel to quantify the impact of evolving defect populations on the thermal conductivity of the fuel. Various dose rates were considered in each phase to reflect the distinct physical conditions typically encountered in light water reactors (LWRs). The model results showed strong alignment with experimental data. This integration of physics-based modeling with data-driven techniques offers valuable insights into defect dynamics and their implications for fuel performance under realistic reactor conditions. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Ceramics, Computational Materials Science & Engineering, Other |