| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
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| Presentation Title |
Fabrication and Characterization of Uranium Carbide |
| Author(s) |
Adrien J. Terricabras, Arjen van Veelen, Erofili Kardoulaki, Scarlett Widgeon Paisner, Timothy Coons, Joshua White |
| On-Site Speaker (Planned) |
Adrien J. Terricabras |
| Abstract Scope |
Uranium carbide have been investigated as a potential fuel candidate for advanced reactors and nuclear thermal propulsion due to its attractive properties. Historical data showed large uncertainties due to impurities and sintering issues. Minute differences in feedstock preparation will result in hypo- or hyper-stoichiometric UC, greatly affecting its physical, thermal, and mechanical properties and overall composition. The lack of recent experimental data on well characterized feedstock and the discrepancies between existing data hinders the development of accurate models. Two different UC feedstocks were prepared using arc melting and carbothermic reduction. Chemical composition was determined using X-ray diffraction, and carbon/oxygen content was measured using combustion analysis. Thermo-physical properties were characterized using laser flash analysis, differential scanning calorimetry and dilatometry. Extended X-ray absorption fine-structure measurements were conducted to study the local structure pre and post sintering. Results from this study will be discussed and compared to historical work published on uranium carbide. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Ceramics |