About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Metallic Fuels - Design, Fabrication, and Characterization
|
| Presentation Title |
Interactions between U-10Mo fuel with a burnable matrix |
| Author(s) |
Geoffrey L. Beausoleil, Cynthia Adkins, Tammy Trowbridge, Laura Sudderth |
| On-Site Speaker (Planned) |
Geoffrey L. Beausoleil |
| Abstract Scope |
In order to improve heavy metal loading in dispersion fuel designs, a uranium-niobium-zirconium alloy was developed as a matrix material for use in dispersion fuels. The alloy produced is U0.22Nb0.58Zr0.20 and is shown to be a stable BCC system, which is important for reliable fission gas retention and minimal swelling behavior. The fuel was then irradiated as a diffusion couple with U-10Mo (10 wt%) at multiple temperatures to assess the potential interaction of the matrix alloy with enriched fuel samples. Scanning electron microscopy (SEM) and electron energy dispersive spectroscopy (EDS) was performed to assess the chemical interactions of the fuel and matrix materials. Results showed minimal interaction and thus good chemical impermeability of the matrix material alongside the fuel. This demonstrates a potential for a uranium based matrix which can enhance fuel performance and proliferation resistance. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Composites, Other |