| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
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| Presentation Title |
Investigating Microstructural and Local Thermal Conductivity Changes in Irradiated U-Zr Annular Fuel |
| Author(s) |
Mary Elizabeth Sevart, Daniele Salvato, Mitchell Mika, Fei Xu, Tiankai Yao, Luca Capriotti, Assel Aitkaliyeva |
| On-Site Speaker (Planned) |
Mary Elizabeth Sevart |
| Abstract Scope |
Annular uranium-zirconium (U-Zr) based fuels have been shown to have vastly different constituent redistribution and microstructural evolution than their solid counterparts. Annular fuels primarily consist of two constituent redistribution zones while solid fuels consist of three primary redistribution zones. The microstructural and constituent redistribution changes after irradiation are not well understood for annular geometries, and more experimental data is necessary for the quantification of fuel performance and efficiencies for annular U-Zr fuels. This work will investigate the constituent redistribution and associated phase regions, porosity, and local thermal conductivity to better understand annular fuel behavior during irradiation. These results will have important implications in understanding overall mass transfer and lanthanide movements in the fuel as well as the effects of constituent redistribution on local thermal conductivity. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Machine Learning |