About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Metallic Fuels - Design, Fabrication, and Characterization
|
| Presentation Title |
Thermal Expansion and Neutron Cross-section of U-Mo fuel to 1000C |
| Author(s) |
Sven C. Vogel, Haley D. Guthrie, Seth D. Imhoff, Kara E. Luitjohan, Alex M. Long, Melissa Thrun |
| On-Site Speaker (Planned) |
Sven C. Vogel |
| Abstract Scope |
Low-enriched uranium-10 wt.% molybdenum (LEU-10wt.%Mo) is of interest for the fabrication of monolithic fuels to replace highly-enriched uranium (HEU) dispersion fuels in high performance research and test reactors around the world. In this presentation we report on the thermal expansion behavior of U-7wt.%Mo, U-10wt.%Mo, and U-13wt.%Mo characterized by neutron diGraction between room temperature and 1000C. Simultaneously collected energy-resolved neutron imaging data also allows to measure the changes in nuclear cross-sections between ambient conditions and 1000C. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, Mechanical Properties |