| 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 |
Room Temperature Oxidation Mechanisms of Uranium Monocarbide |
| Author(s) |
Adrian R. Wagner, Jennifer K Watkins, Boone Beausoleil, Tiankai Yao, Seongtae Kwon |
| On-Site Speaker (Planned) |
Adrian R. Wagner |
| Abstract Scope |
As advanced reactors become reality, the need for high uranium density fuels with superior thermomechanical properties are needed. One fuel type being considered is uranium monocarbide because it has higher uranium loading, melting temperature, and thermal conductivity when compared to uranium dioxide. However, recent efforts to fabricate UC fuel pellets at Idaho National Laboratory have given insight into its inconsistent oxidation tendencies during fabrication and storage. The aim of this work was to elucidate potential causes of room temperature oxidation of uranium monocarbide fuel pellets. Pellets were fabricated using a powder metallurgical process and samples were analyzed via SEM and TEM. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Ceramics |