| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramic Materials for Nuclear Energy Research and Applications
|
| Presentation Title |
Diffusion Properties in Uranium-plutonium Mixed Oxides: Atomic Scale Investigation of the Effect of Composition and Chemical Disorder |
| Author(s) |
Marjorie Bertolus, Maria Chiara Notarangelo, Didier Bathellier, Michel Freyss, Emeric Bourasseau, Luca Messina |
| On-Site Speaker (Planned) |
Marjorie Bertolus |
| Abstract Scope |
Mixed uranium-plutonium oxides are used as fuel in pressurized water nuclear reactors and are the reference fuel for future Generation IV sodium-cooled fast reactors.
Atom transport properties are at the origin of important phenomena taking place in (U,Pu)O2 fuels during irradiation, in particular the redistribution of Pu in the fuel and the oxygen diffusion, which governs the local oxide/metal ratio. Therefore, the precise knowledge of diffusion mechanisms and coefficients, starting from the atomic scale, is crucial to model and predict the microstructure evolution of nuclear fuels in reactor.
In the (U,Pu)O2 solid solution, uranium and plutonium ions are distributed randomly on the cationic sublattice, giving rise to an extremely large amount of possible configurations. We will present the results of a systematic analysis using atomic scale methods of the effect of plutonium concentration and local disorder on the formation and migration energy of radiation-induced defects, in particular bound Schottky defects. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Modeling and Simulation, |