| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramics and Ceramic-based Composites for Nuclear Fission Applications
|
| Presentation Title |
Uranium Enrichment Homogeneity Study on HALEU/LEU UO2 Fuel Pellets |
| Author(s) |
Jennifer K. Watkins, Adrian Wagner, Daniel Murray, Uriel Santoro |
| On-Site Speaker (Planned) |
Jennifer K. Watkins |
| Abstract Scope |
Quantification and homogeneity of uranium enrichment in nuclear fuels, specifically during production, have important consequences for neutronics, heat distribution, and fuel life cycles. Advanced reactor concepts, using a smaller design for increased power per volume, will all rely on HALEU fuel (isotopically enriched to 5%-20% U235) for operation. This HALEU fuel will provide longer life cores, increased efficiencies, and improved fuel utilization. Idaho National Laboratory’s unique ability to handle and produce high enriched uranium fuel has led to the successful fabrication of monolithic HALEU UO2 fuel pellets according to commercial specifications using traditional powder metallurgy processes and pressureless sintering methods. The enrichment homogeneity was examined using a focused ion beam equipped with time-of-flight secondary ion mass spectrometry enabling isotopic mapping. The enrichment homogeneity of the HALEU samples were compared to that of depleted UO2 samples and commercially produced LEU UO2 (<5%) pellets to evaluate differences associated with separate production methods. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Ceramics, Characterization |