| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Probing the plastic strength of Fe-Cr alloys by composition-aware dislocation dynamic |
| Author(s) |
Riccardo Civiero, Anter El-Azab |
| On-Site Speaker (Planned) |
Riccardo Civiero |
| 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 resistance to elevated temperatures. These steels are predominantly composed of iron and chromium, with the latter constituting the 8-14 wt.% of the composition. 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. In doing so, 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 findings, including comparison with experimental data. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Modeling and Simulation, Nuclear Materials, Mechanical Properties |