| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
|
| Presentation Title |
Chemical Redistribution of Alloying Elements through Oxide/Metal Interface of Irradiated ZrNbFe Alloys and Its Implication on Corrosion Behavior |
| Author(s) |
Zefeng Yu, Elizabeth Kautz, Hongliang Zhang, Anton Schneider, Yongfeng Zhang, Sten Lambeets, Arun Devaraj, Adrien Couet |
| On-Site Speaker (Planned) |
Adrien Couet |
| Abstract Scope |
Transport of species through zirconium oxide is affected by oxide doping, resulting in complex corrosion mechanism. In this study, we focus on elemental redistributions across the oxide/metal interface. In-situ atom-probe-tomography experiments, where the needle is pre-oxidized in O2 at 260°C, have been performed on unirradiated and 1 dpa proton irradiated ZrNbFe model alloys to characterize chemical redistribution across the oxide/metal interface. The results show that solute Nb redistributes across the oxide/metal interface, reducing the Nb/Zr ratio in the metal relative to the oxide, while the Fe does not redistribute. High-Resolution Transmission-Electron-Microscopy is performed to measure oxide thickness and determine its microstructure under similar corrosion conditions. Density functional theory calculations on solute thermodynamics are performed in metal and oxide matrices to tentatively explain, and compare to, the experimental observations. The implications in terms of oxide doping and transport of oxidizing species through the protective oxide under irradiation are discussed. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Environmental Effects, Nuclear Materials |