| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments II
|
| Presentation Title |
Thermomechanical, Lead Corrosion and Thermal Stability Assessment of Innovative Alumina Forming Austenitic Alloys for LFRs |
| Author(s) |
Enrico Virgillito, Daniele De Caro, Antonino Meli, Davide Loiacono, Francisco Garcia Ferrč |
| On-Site Speaker (Planned) |
Enrico Virgillito |
| Abstract Scope |
The advancement of the new generation of Lead-cooled Fast Reactors (LFRs) encounters the key challenge of long-term degradation of structural materials when exposed to liquid lead (Pb). Current research identifies alumina-forming austenitic (AFA) steels as a promising material class for structural applications in LFRs. A novel range of AFA steel compositions has been determined through thermodynamic simulations to predict mechanical properties, corrosion resistance, and thermal stability. Thermomechanical tests are conducted using a Gleeble machine to simulate traditional forming processes. The behavior of the nominal simulated and experimental alloys is compared through Pb corrosion tests lasting up to 1000 hours at 600 °C. Additionally, the thermal stability of selected compositions is evaluated by oven ageing. Comprehensive bulk characterization techniques, including SEM, XRD, and OM, are utilized to analyze microstructure and phase transformations. Finally, the behavior under irradiation effects will be examined utilizing an advanced in-situ TEM setup with heavy ion irradiation. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Environmental Effects, High-Temperature Materials |