| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Accelerated Evaluation of Creep Behavior in Nuclear Reactor Structural Alloys |
| Author(s) |
Minh-Tam Hoang, Eric Hintsala, Kevin Schmalbach, Douglas Stauffer, Jobin Joy, Anjana Talapatra, Laurent Capolungo, John Carpenter, Benjamin Eftink, Nathan Mara |
| On-Site Speaker (Planned) |
Minh-Tam Hoang |
| Abstract Scope |
Advanced reactor designs require materials that can withstand high temperatures, irradiation damage, and corrosion. However, current qualification frameworks involve extensive testing, delaying their commercialization in the nuclear industry. This study introduces a high-throughput testing protocol to evaluate the creep behavior of advanced alloys using nano/microindentation and modeling. Indentation strain rate jump tests on Grade 91 up to 700°C in an inert atmosphere revealed stress exponents consistent with power-law creep. By extracting physical information from high-temperature indentation, we develop physics-based models to predict the creep rupture lifetime of advanced alloys. This protocol is demonstrated on Grade 91 and 347H stainless steels. Additionally, additive manufacturing (AM) technologies offer the potential to tailor microstructures and properties with near-net-shape manufacturing for nuclear reactor applications. Given the spatial dependencies within AM materials, a combination of nano/microindentation mapping and microscopy techniques (SEM-EBSD/TEM) is used to correlate microstructural features with local mechanical properties, initially focusing on 316H. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Additive Manufacturing, High-Temperature Materials, Modeling and Simulation |