| 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 |
Correlation of Thermal Properties with Local Microstructure of Irradiated Sodium-Bonded U-Zr Metallic Fuel |
| Author(s) |
Cynthia Adkins, Ethan Hisle, Narayan Poudel, Tsvetoslav Pavlov, Luca Capriotti |
| On-Site Speaker (Planned) |
Cynthia Adkins |
| Abstract Scope |
This study focuses on the thermal transport properties, specifically thermal conductivity and thermal diffusivity, of sodium-bonded irradiated uranium-zirconium (U-Zr) metallic fuel as the initial design for use in advanced reactors. The research aims to understand the correlation between microstructure and thermal conductivity, both on the macro and mesoscale, for pre- and post-irradiated U-10Zr alloy at varying atom percent burnup. These experimental findings contribute valuable insights into the thermal conductivity and microstructure relationship in metallic fuels, particularly in the U-10Zr system. The research improves the accuracy of effective thermal conductivity calculations and provides enhanced tools for fuel performance models. The study's significance lies in its unique collection of data on both the macro and mesoscale, setting a foundation for further advancements in understanding and optimizing the thermal properties of metallic fuels, ultimately benefiting the development of next-generation nuclear fast reactors. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, |