| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Composite Materials for Nuclear Applications II
|
| Presentation Title |
Microstructure and Thermophysical Property Characterization of U-ZrHx Fuel Fabricated by Powder Metallurgy |
| Author(s) |
Tyler Scott Smith, Caitlin Taylor, Michael Hahn, Erik Luther, Thomas Nizolek, Aditya Shivprasad |
| On-Site Speaker (Planned) |
Tyler Scott Smith |
| Abstract Scope |
Uranium-zirconium hydride (U-ZrHx) fuel is under consideration for microreactor applications. This type of fuel combines both fuel and moderator into a single material, and has proven to be a useful fuel type for TRIGA reactors. However, the ability to retain hydrogen and mitigate swelling at elevated temperatures and burnup becomes essential for fuel success in these applications. LANL has developed a powder metallurgy method for fabricating high density U-ZrHx fuel pellets. As-fabricated pellets were characterized using x-ray diffraction, microscopy, and thermophysical property measurements. This talk will overview these results and specifically address the thermal expansion, thermal conductivity, thermal diffusivity, and hydrogen retention of this fuel type at elevated temperatures. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Powder Materials, Nuclear Materials, Other |