About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Modern FeCrAl-ODS Alloys: Addressing Critical Challenges for Current and Advanced Reactor Operation |
| Author(s) |
Caleb Massey, David T. Hoelzer |
| On-Site Speaker (Planned) |
Caleb Massey |
| Abstract Scope |
Abstract: A new initiative within the DOE Innovative Nuclear Materials program aims to develop modern oxide dispersion strengthened (ODS) FeCrAl alloys to address critical challenges identified in legacy FeCrAl alloys. These challenges include irradiation hardening and embrittlement at lower operational temperatures (<300 °C), as well as particle instability at high irradiation doses under liquid metal fast reactor operating temperatures (350–550°C). Two ODS FeCrAl alloys were produced by mechanical alloying of gas-atomized, pre-alloyed powder (Fe-16Cr-4Al-2Mo-0.2Y wt.%) supplied by Powder Alloy Corp., along with additions of CeO₂ and Y₂O₃ powders. Microstructural characterization of the new FeCrAl alloys using scanning electron microscopy (SEM), electron backscattered diffraction (EBSD), and atom probe tomography (APT) revealed grain sizes of ~450–520 nm and a high number density of nanoscale oxide particles with Ce–Y–O compositions that contained no Al. The mechanical properties of these new FeCrAl-ODS alloys are directly compared with prior FeCrAl-ODS variants produced for accident-tolerant fuel cladding activities within the AFC program, as well as with legacy materials such as PM2000 and APMT. The results demonstrate a combination of high strength and fracture toughness at operational temperatures relevant to current light water reactors and liquid metal fast reactors. |
| Proceedings Inclusion? |
Planned: |