About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Metallic Fuels - Design, Fabrication, and Characterization
|
| Presentation Title |
Assessing Thermal Conductivity in U-Zr Fuels: A Comparison of Modeling and Experimental Results |
| Author(s) |
Mary Elizabeth Meyer, Yogesh Kumar, Ethan Hisle, Fei Xu, Tiankai Yao, Michael Tonks, Assel Aitkaliyeva |
| On-Site Speaker (Planned) |
Mary Elizabeth Meyer |
| Abstract Scope |
A new geometry of uranium-zirconium (U-Zr) fuels is under investigation with a manufactured annulus for the reduction of cladding stress at higher burnups. Preliminary experimental data shows distinct differences in fuel behaviors, including porosity development and constituent redistribution, between solid and annular geometries. The ability to accurately simulate the behavior of annular U-Zr fuels under irradiation is required for fuel qualification; however, the current lack of experimental data for annular geometries is hindering modeling efforts. This presentation will provide a comprehensive analysis of thermal conductivity in an annular, U-10Zr fuel rod and compare the current state of the fuel performance model BISON with experimental thermal conductivity data. This comparison will highlight the need for further experimental work on annular U-Zr fuels to guide fuel performance model development. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, |