| About this Abstract |
| Meeting |
2023 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
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| Presentation Title |
High Temperature Steam Oxidation Performance of Alloyed, High Density Fuel Composite: U<sub>3</sub>Si<sub>2</sub> + 50wt% UB<sub>2</sub> |
| Author(s) |
Geronimo Robles, Joshua T. White, Scarlett Widgeon Paisner, Elizabeth Sooby |
| On-Site Speaker (Planned) |
Geronimo Robles |
| Abstract Scope |
Recently, advanced nuclear reactor fuel development has investigated high density fuel (HDF) compounds and composites like UN/U<sub>3</sub>Si<sub>2</sub> and UB<sub>2</sub>/U<sub>3</sub>Si<sub>2</sub> as drop-in replacements of traditional UO<sub>2</sub> for their superior uranium density and thermal conductivity. Despite improved fuel structural stability, economy, and safety of these HDF’s, mitigating the energetic pulverization of U<sub>3</sub>Si<sub>2</sub> when exposed to high temperatures and oxidants possible during off-normal conditions remains paramount. Techniques like compositing U<sub>3</sub>Si<sub>2</sub> with UB<sub>2</sub> at concentrations <10wt% has achieved a delay in oxidation by >100°C and alloying and oxide dispersion strengthening (ODS) U<sub>3</sub>Si<sub>2</sub> have also shown delays.
Reported here, U<sub>3</sub>Si<sub>2</sub> + 50wt% UB<sub>2</sub> HDF composites are fabricated with Al and Al<sub>2</sub>O<sub>3</sub> additives. As fabricated and heat-treated samples are oxidized and characterized to examine the impact of complex microstructure on performance in high temperature oxidizing atmospheres. Fabricability challenges for each composition are reported. SEM/EDS and p-XRD analysis and thermogravimetric data related changes to performance. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Other, High-Temperature Materials, Nuclear Materials |