About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments III
|
| Presentation Title |
Critical Assessment of Corrosion Resistance and Mechanical Integrity of traditional and advanced steels in liquid sodium. |
| Author(s) |
Marie Romedenne, Praneeth Bachu, Sam Bell, Tim Graening, Caleb Massey |
| On-Site Speaker (Planned) |
Marie Romedenne |
| Abstract Scope |
Advanced sodium fast reactors require structural materials that maintain mechanical integrity and corrosion resistance in the harsh environment of high-temperature liquid sodium (Na) coolant. Traditional materials, such as austenitic (316H, D9) and ferritic-martensitic (T91, HT9) alloys, have performed acceptably in Na-cooled reactors below 500 °C. However, their mechanical and corrosion stability deteriorates significantly above 600 °C. In contrast, newly developed nanostructured alumina-forming austenitic (AFA) alloys are designed for enhanced performance at elevated temperatures (≥ 650 °C). Despite their promising attributes, the compatibility of AFA alloys with liquid sodium has not been fully established. This study evaluates the performance of both traditional steels and AFA alloys in static, commercially sourced liquid sodium at 700 °C for 1,000 hours, assessing the effects of mechanical stress and liquid metal corrosion. Post-exposure analyses using scanning electron microscopy (SEM), transmission electron microscopy (TEM), and compositional analysis aim to investigate compositional changes and substrate integrity. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
High-Temperature Materials, Characterization, Nuclear Materials |