| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification of Nuclear Materials Integrating Experiments, Modeling, and Theories
|
| Presentation Title |
High Throughput Assessment of Creep Behavior of Advanced Nuclear Reactor Structural Alloys by Nanoindentation |
| Author(s) |
Minh-Tam Hoang, Kevin Schmalbach, Eric Hintsala, Douglas Stauffer, Justin Cheng, Moujhuri Sau, Ben Eftink, Nathan Mara |
| On-Site Speaker (Planned) |
Minh-Tam Hoang |
| Abstract Scope |
Advanced Fe-based alloys are favored for use in nuclear reactors due to their promising performance in terms of radiation resistance, high-temperature strength, and corrosion resistance. Nanoindentation is employed to quantify the creep behavior of materials, facilitating the development of predictive tools to assess the material’s performance and predict their long-term behavior under extreme conditions. Here, we obtain mechanism-dependent parameters such as strain rate sensitivity, activation energy, and activation volume of FeCrAl alloys (Kanthal APM and APMT). Strain rate jump tests are conducted to assess the mechanical response of the alloy and reveal that both alloys exhibit stress exponents at temperatures of 600oC and higher of approximately 7-10, suggesting that power-law creep behavior as the dominant deformation mechanism. Transmission electron microscopy of the FeCrAl alloys is performed to investigate changes in microstructure after exposure to high temperatures. Results will be discussed in the context of mechanism-dependent inputs for mesoscale microstructurally-informed models. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, Iron and Steel |