| 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 |
Thermochemical Investigation of Advanced Reactor Fuels and Fuel-clad Chemical Interaction |
| Author(s) |
Elizabeth S. Sooby |
| On-Site Speaker (Planned) |
Elizabeth S. Sooby |
| Abstract Scope |
Both the evolution of commercial reactor fuel forms and development of the next generations of reactors have sparked a demand to further understand and predict the behavior of advanced reactor fuel forms. Commercial fuel vendors are considering higher uranium density fuels to enhance fuel economy and better accommodate accident tolerant cladding, and the leading designs for small modular reactors are looking toward particle fuel architectures. A number of data gaps and/or inconsistencies exist for these lesser known fuel concepts. Of particular interest are the as fabricated microstructures of these novel fuels, the microstructural evolution during thermal synthesis and processing, and particularly fuel-clad and fission product-clad chemical interaction for novel fuel forms. Presented will be the experimental investigation of high uranium density fuel fabrication, including as-fabricated and thermally annealed microstructures. Additionally, limited experimental assessments of fuel and fission product interactions with silicon carbide. |
| Proceedings Inclusion? |
Planned: |