About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Long-Term Aging Effects of Alloy 709 |
| Author(s) |
Xuesong Fan, Brad Hall, Jeremy L. Moser, Yanli Wang |
| On-Site Speaker (Planned) |
Xuesong Fan |
| Abstract Scope |
Due to its exceptional high-temperature strength, creep resistance, and oxidation behavior, Alloy 709, an advanced austenitic stainless steel, has been selected for potential use as a Class-A construction material in high-temperature reactor applications. As part of a comprehensive staged qualification strategy aimed at enabling longer design lifetimes, significant effort has been dedicated to developing mechanical property data at elevated temperatures, which have been previously reported. However, understanding the effects of long-term thermal aging on Alloy 709 is equally critical to ensure its structural reliability and performance over extended service periods. In this study, three commercially produced heats of Alloy 709 were subjected to isothermal aging at six different temperatures for durations up to 10,000 hours. A systematic study including mechanical testing and microstructural characterization was performed to evaluate the strength, ductility, and phase stability. The results provide key insights into the alloy’s aging behavior and implications for high-temperature reactor applications. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
High-Temperature Materials, Iron and Steel, Mechanical Properties |