About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Microstructure–Tensile Property Correlation in Neutron-Irradiated Fe-10Cr and Fe-14Cr ODS Alloys at 590°C to 20 dpa |
| Author(s) |
Yan-Ru Lin, Viacheslav Kuksenko, Steven Zinkle, David Hoelzer, Amy Gandy, TS Byun |
| On-Site Speaker (Planned) |
Yan-Ru Lin |
| Abstract Scope |
Oxide dispersion-strengthened (ODS) alloys offer improved high-temperature strength and radiation resistance, but their mechanical performance under high-dose neutron-irradiation remains uncertain. This study investigates microstructure–tensile property correlations in Fe-10Cr (M4 and M5) and Fe-14Cr (14YWT-SM12 variants) ODS alloys irradiated at 590°C to 20 dpa in HFIR at ORNL. M4 and M5 were compared to assess the effect of W addition in M4, while the 14YWT variants, identical in composition but differing in heat treatments, enabled evaluation of sink strength effects from the initial microstructure. Microstructural characterization was performed on the same SS-J3 tensile specimens, taken from grip sections. Transmission electron microscopy and atom probe tomography were used to analyze defects, grain boundary segregation, and oxide stability. Post-irradiation reductions in tensile strength and increases in uniform elongation were linked to corresponding changes in microstructure. Segregation of W and its transmutation products to grain boundaries contributed to ductility degradation. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, High-Temperature Materials |