| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
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| Symposium
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Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
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| Presentation Title |
Chemical Compatibility of UC/UO2 Composites for Accident Tolerant Fuel |
| Author(s) |
Steven Jay Cavazos, Scarlett Widgeon Paisner, Ian Porter, Joshua T. White |
| On-Site Speaker (Planned) |
Steven Jay Cavazos |
| Abstract Scope |
Accident tolerant fuels are of significant interest as they are designed to exhibit superior fuel performance by increasing thermal conductivity and uranium density compared to traditional UO2. While UCO fuel kernels have been investigated for advanced gas reactors, UC/UO2 composite pellets have yet to be fully explored for LWR deployment. In this study, a comprehensive evaluation on the synthesis and material properties was performed on sintered UC/UO2 pellets. The U-O-C ternary phase diagram was calculated in Thermo-Calc and used to inform experimental conditions to investigate the chemical compatibility. UO2 and UC diffusion couples were studied to observe reactivity between the two phases up to 1800 °C. SEM/EDS was done to observe the microstructures at the interface and to observe uranium metal formation at the grain boundaries. The results from this study aim to inform future fabrication efforts of the UC/UO2 composite fuels. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Ceramics |