About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Comparison of Ion Irradiation Behavior of Wrought FeCrAl and Additively Manufactured and Powder Metallurgy ODS FeCrAl |
| Author(s) |
Thomas Siggillino, Steven J. Zinkle, Caleb P. Massey |
| On-Site Speaker (Planned) |
Thomas Siggillino |
| Abstract Scope |
FeCrAl alloys are being explored as a more radiation resistant and accident tolerant alternative to Zr-based alloys in nuclear reactor fuel cladding, with even greater radiation resistance achieved by adding oxide dispersoids to FeCrAl to produce oxide dispersion strengthened (ODS) variants. Additive manufacturing with in-situ oxide precipitation has been explored to improve the flexibility and cost of ODS FeCrAl production. However, data is currently lacking on the response of additively manufactured ODS FeCrAl to ion irradiation. In this work, a comparison is made between wrought FeCrAl, FeCrAl with dissolved Y additively manufactured using directed energy deposition in an oxygen environment, and a powder metallurgy ODS FeCrAl alloy extruded at 1000°C. All three materials were irradiated with 10 MeV Cu3+ ions at 300°C to a midrange dose of 10 dpa at a dose rate of 3×10-4 dpa/s. The microstructural and mechanical property responses were characterized using STEM and nanoindentation. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Additive Manufacturing, Characterization |