| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Unraveling the roles of grain boundary chemistry and stress state on the oxidation response of Ni-Cr alloys |
| Author(s) |
Elizabeth Jane Kautz, Karen Kruska, Ziqing Zhai, Robert McRobie, Josephine Hartmann, Daniel Schreiber, Matthew Olszta |
| On-Site Speaker (Planned) |
Elizabeth Jane Kautz |
| Abstract Scope |
Ni-based alloys are used in pressurized water reactors and considered for advanced reactor systems but are susceptible to intergranular stress corrosion cracking. Here, the corrosion behavior of Ni-5Cr (at. %) was studied during a 4-point bend test in a gas atmosphere at 420°C for 72 hours with controlled oxygen partial pressure. This test aimed to understand if applied stress leads to breakdown of passivity at grain boundaries. Complementary electron microscopy and atom probe tomography characterized the chemical composition differences at grain boundaries oxidized under tensile and compressive stress. Our findings show variability in cracking and oxide thickness between tensile and compressive stress states, and variability in grain boundary chemistry. Understanding the roles of stress state and grain boundary chemistry on oxidation response and protective nature of the oxide film will be presented, and how advanced experimental methods can help unravel separate effects will be discussed. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Environmental Effects, Characterization |