About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification Methods for Nuclear Reactor Structural Materials
|
| Presentation Title |
Irradiation effects on microstructure and mechanical properties of oxide dispersion strengthened steel MA956 |
| Author(s) |
Ryan Charles Sundburg, Elizabeth Getto, Brad Baker, Matthew Swenson |
| On-Site Speaker (Planned) |
Ryan Charles Sundburg |
| Abstract Scope |
Oxide dispersion strengthened (ODS) steels such as MA956 are prime candidates for structural components in advanced nuclear reactors. These materials historically demonstrate both mechanical and microstructural evolution through the introduction of irradiation. Samples were irradiated to both 1 dpa and 25 dpa both at 400 °C using self-ion irradiation with Fe2+ ions along with an unirradiated sample. Changes in hardness were compared using nanoindentation to investigate macroscopic mechanical property changes. Microstructural features such as oxide dispersoids and nanoclusters were investigated with the use of scanning transmission electron microscopy (STEM) and atom probe tomography (APT). Morphology changes were used to develop a mathematical model to understand morphology change as a function of irradiation dose. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Characterization |