About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructure-Sensitive Modeling Across Length Scales: An MPMD/SMD Symposium in Honor of David L. McDowell
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| Presentation Title |
Plastic Strength of Irradiated Fe-Cr Alloys for Structural Applications in Fusion Reactors |
| Author(s) |
Anter A. El-Azab |
| On-Site Speaker (Planned) |
Anter A. El-Azab |
| Abstract Scope |
ODS ferritic and reduced activation ferritic-martensitic steels, as Eurofer-97, JLF-1 and MA957, represent leading candidate alloys for nuclear fusion. This interest is due to their superior mechanical properties and irradiation stability. These steels are predominantly composed of Fe and Cr, with the latter being 8-14 wt.% of the alloy. It has been observed that Fe-Cr alloys exhibit composition fluctuations and microstructure changes when exposed to neutron or ion irradiation. In this research we investigate the impact of such changes on the plastic strength of Fe-Cr system as a base alloy for that class of ferritic alloys for fusion. We combine molecular dynamics results for the composition and temperature dependent dislocation mobility, together with the composition and microstructure information reported for thermally treated and irradiated Fe-Cr systems, into composition-aware dislocation dynamics simulations. This presentation summarizes the approach and results for the plastic strength of Fe-Cr alloys, including comparison with experimental data. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Computational Materials Science & Engineering, Mechanical Properties, Nuclear Materials |