| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramic Materials for Nuclear Energy Research and Applications
|
| Presentation Title |
Advanced Characterization and Modeling of Nanoprecipitates in Spent Nuclear Fuel |
| Author(s) |
Lingfeng He, Mukesh Bachhav, Chao Jiang |
| On-Site Speaker (Planned) |
Lingfeng He |
| Abstract Scope |
Spent nuclear fuel undergoes significant microstructural and chemical evolution during reactor operations. Some fission products are retained within the UO2 matrix in solid solution, while the inert gases, xenon, krypton, and the 4d group metals, molybdenum, technetium, ruthenium, rhodium, and palladium are trapped as bubbles and metallic precipitates, respectively in the UO2 matrix. In this work, atomic resolution microstructure and chemical composition of nanoprecipitates in spent UO2 fuel from Belgian Reactor 3 are characterized using high resolution scanning transmission electron microscopy, Super-X energy dispersive X-ray spectroscopy and atom probe tomography techniques. Density-functional theory is utilized to understand the formation mechanism of nanoprecipitates and their phase relationships with UO2 matrix. Molecular dynamics simulation is used to calculate the fission gas bubble pressure. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, Modeling and Simulation |