About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Radiation Induced Segregation on Dislocation Loops in Ultra-High Purity Fe-Cr Binary Alloys |
| Author(s) |
Siwei Chen, Quanyou Zhang, Haixuan Xu, Steven J. Zinkle |
| On-Site Speaker (Planned) |
Siwei Chen |
| Abstract Scope |
Fe-Cr based ferritic steels are leading candidate structural materials for key components in fusion and Gen IV nuclear reactors. Radiation-induced segregation (RIS) on dislocation loops is believed to contribute to irradiation hardening, inducing a loss of ductility. In this study, we performed 8 MeV Fe ion irradiations on ultra-high purity Fe-3Cr and Fe-10Cr alloys at 300 and 500 °C (10-4 dpa/s) at a midrange (1 μm depth) dose of 0.35 dpa. The analysis was conducted using scanning transmission electron microscopy with energy dispersion spectroscopy (STEM-EDS), supported by computational simulations. Cr segregation on dislocation loops was observed at 500 °C, while it was negligible at 300 °C. STEM-EDS maps revealed the Cr enrichment within dislocation loops (compression stress region), and the non-uniform Cr segregation between different dislocation loops. The oscillatory behavior of the Cr concentration profile across the edge-on dislocation loops was observed in Fe10Cr alloy, but not in Fe3Cr alloy. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Iron and Steel, Characterization |