| 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 |
Impact of Uranium Feedstock Impurities on the Microstructure and Oxidation Resistance of Uranium Nitride (UN) |
| Author(s) |
Max Salata-Barnett, Tim Abram |
| On-Site Speaker (Planned) |
Max Salata-Barnett |
| Abstract Scope |
Uranium nitride (UN) is a promising advanced fuel candidate due to its high uranium density and thermal conductivity. However, its oxidation resistance is a critical factor in determining its suitability for reactor applications. This study explores the influence of various impurities in the starting uranium material on the microstructure and oxidation resistance of UN. Three different uranium feedstocks with distinct elemental compositions were used to synthesize UN via the hydride/nitride route. The resulting powder and pellets, manufactured via spark plasma sintering, are characterised using XRD, EDX (SEM/TEM), and STA. Thermogravimetry results from synthetic air and steam oxidation up to 1000°C will be presented, with analysis of how different impurities affect the microstructural characteristics and oxidation performance of UN. This research, in collaboration with Boise State University, Texas A&M University, and Los Alamos National Laboratory, aims to optimize UN production for improved oxidation resistance. |
| Proceedings Inclusion? |
Planned: |