| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Environmentally Assisted Cracking: Theory and Practice
|
| Presentation Title |
Exploring Environmentally-Assisted Cracking in Liquid Metal and Molten Salt Advanced Reactor Coolant Environments |
| Author(s) |
Samuel A. Briggs, Dustin Mangus, Jake Quincey, Xavier Quintana, Guillaume Mignot, Julie D Tucker |
| On-Site Speaker (Planned) |
Samuel A. Briggs |
| Abstract Scope |
While complex materials degradation modes, including stress corrosion cracking, corrosion fatigue, and irradiation-assisted stress corrosion cracking, have been studied extensively for light water reactor environments, these phenomena are not well-understood in proposed advanced reactor systems. Due to higher temperatures and distinct corrosion mechanisms, these effects are expected to manifest in significantly different ways in these non-aqueous coolant environments. Oregon State University has recently developed unique facilities enabling testing of fracture mechanics-based environmentally-assisted cracking in liquid sodium and molten salt environments. These facilities combine some mechanical loading mechanism (e.g., a traditional electronic actuator) with a controlled coolant environment of interest, enabling various types of standardized tests exploring environmentally-assisted cracking within a wide range of operating conditions relevant to several preeminent advanced reactor designs. Initial testing has focused on 316L stainless steel. Slow strain rate tests in molten LiF-NaF-KF (FLiNaK) eutectic salts and U-bend tests in liquid sodium environments will be discussed. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Environmental Effects, Nuclear Materials, Mechanical Properties |