About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Presentation Title |
Morphology and Interaction of 〈100〉 Dislocation Loops Under Ion Irradiation in High Purity Fe-Cr Binary Alloys |
| Author(s) |
Siwei Chen, Anthony Tom, Li Yang, Brian D. Wirth, Steven J. Zinkle |
| On-Site Speaker (Planned) |
Siwei Chen |
| Abstract Scope |
Fe-Cr based ferritic steels are essential structural materials used in the core components of nuclear reactors. The formation and interaction of dislocation loops under particle irradiation can significantly affect the mechanical properties of these materials. In this study, we investigate the morphology and interaction of 〈100〉 dislocation loops under ion irradiations through a combination of experimental observations and molecular dynamic (MD) simulations. 800 keV proton irradiations were conducted at 350 and 450 °C on Fe-10Cr alloy, and 8 MeV Fe3+ ion irradiation was performed at 500 °C on both Fe-3Cr and Fe-10Cr alloys. Post irradiation scanning transmission electron microscope (STEM) revealed isolated square-shaped 〈100〉 loops, 1-D clustering of square 〈100〉 loops, and coalesced 〈100〉 loops with edges aligned along the 〈100〉 crystallographic directions at temperatures of 350-500 °C. The increased Cr content resulted in a higher perimeter to area ratio of the loop. MD simulation was conducted to explain the experimental findings. The formation energy of square dislocation loops was found to be lowest at elevated temperatures compared to loops with other shapes, such as circle, diamond, and hexagon. Two 5 nm square loops on parallel habit planes were introduced to the simulation system to explore the loop interaction at 500 °C. We propose a fast 1-D glide and core diffusion climb model for the 〈100〉 loop evolution based on the experimental observations and MD simulations. |
| Proceedings Inclusion? |
Undecided |