About this Abstract |
Meeting |
2024 TMS Annual Meeting & Exhibition
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Symposium
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Ceramics and Ceramic-based Composites for Nuclear Fission Applications
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Presentation Title |
Response of the U<sub>3</sub>Si<sub>2</sub> + 50 wt%UB<sub>2</sub> Composite Alloyed with Al, Al<sub>2</sub>O<sub>3</sub>, Y and
Y<sub>2</sub>O<sub>3</sub> in High-Temperature Oxidizing Atmospheres |
Author(s) |
Geronimo Robles, Scarlett Widgeon Paisner, Joshua T. White, Elizabeth S. Sooby |
On-Site Speaker (Planned) |
Geronimo Robles |
Abstract Scope |
The development of high density fuel (HDF) compounds has investigated composites, such as U<sub>3</sub>Si<sub>2</sub>/UN and U<sub>3</sub>Si<sub>2</sub>/UB<sub>2</sub>, to take advantage of their high uranium density and thermal conductivity. In composite form, the energetic degradation mechanism of U<sub>3</sub>Si<sub>2</sub> has been improved upon. However, the response to high temperature oxidizing atmospheres (i.e. steam) at 1200°C continues to prevent deployment in advanced nuclear power reactors. Elemental additions such as Al and Y are incorporated with the intent to form a passivating oxide to inhibit oxygen diffusion into the fuel. Alternatively, oxides like Al<sub>2</sub>O<sub>3</sub> and Y<sub>2</sub>O<sub>3</sub> are explored to impart strength as well as corrosion resistance.
Here, work previously detailed on the fabrication of the U<sub>3</sub>Si<sub>2</sub> + 50 wt% UB<sub>2</sub> composite alloyed with Al, Y, Al<sub>2</sub>O<sub>3</sub> and Y<sub>2</sub>O<sub>3</sub> is expanded upon by measuring its oxidation performance. Measurements are
conducted via thermogravimetric analysis under steam environment. Phase analysis is also presented via SEM, EDS, and XRD. |
Proceedings Inclusion? |
Planned: |
Keywords |
High-Temperature Materials, Composites, Nuclear Materials |