| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments II
|
| Presentation Title |
Effects of Sodium Exposure on Tensile Properties of Advanced Reactor Materials |
| Author(s) |
Yiren Chen, Zuotao Zeng, Wei-Ying Chen, Meimei Li |
| On-Site Speaker (Planned) |
Yiren Chen |
| Abstract Scope |
Advanced structural materials such as G91 and A709 show great promise for the next generation of nuclear power systems due to their enhanced high-temperature properties. In this work, the performance of the advanced ferritic and austenitic steels in liquid sodium environments is evaluated. After sodium exposure at 550-600°C for extended periods, the effects of sodium on the microstructure and tensile properties of G91 and A709 are investigated. The impact of sodium on the carbide microstructure of these alloys is discussed. Strong carbide formers such as Ti, V, Nb are critical for the microstructural stability of these advanced alloys, reducing the tendency of decarburization in a low-carbon-activity sodium environment. The information generated from this study can help understand the mechanisms and the kinetics of carbon transfer in the sodium-steel system, providing a technical basis for assessing the service performance of these advanced alloys in sodium-cooled fast reactors. |
| Proceedings Inclusion? |
Planned: |