About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification Methods for Nuclear Reactor Structural Materials
|
| Presentation Title |
Radiation Response of Wrought and Additively Manufactured Alloy 709 Under Dual Ion Irradiation at Reactor-Relevant Conditions |
| Author(s) |
Katherine Baker, Steven J Zinkle |
| On-Site Speaker (Planned) |
Katherine Baker |
| Abstract Scope |
Alloy 709 (A709) is a high-performance austenitic stainless steel under development for high-temperature nuclear systems due to its excellent creep strength and supposed radiation tolerance. However, only limited data exist on its irradiation behavior, particularly for components produced via additive manufacturing (AM) which introduces distinct microstructural features. We studied the radiation response of wrought and laser powder bed fusion AM A709 subjected to solution annealing, aging, and cold work thermomechanical treatments. Dual ion irradiations using 9 MeV Fe ions with helium co-implantation were conducted at 340 to 675°C to midrange doses of 2 to 150 dpa, simulating damage conditions across light water and fast reactor regimes. Post-irradiation characterization including TEM, STEM-EDS, and nanoindentation will evaluate swelling, hardening, dislocation structures, and radiation-induced segregation. Results will provide insight into the microstructural stability of A709 under reactor-relevant conditions and support its qualification for advanced nuclear applications. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Additive Manufacturing, High-Temperature Materials, Nuclear Materials |