About this Abstract |
Meeting |
MS&T22: Materials Science & Technology
|
Symposium
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Tackling Structural Materials Challenges for Advanced Nuclear Reactors
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Presentation Title |
Assessing Materials Susceptibility to Environmentally-assisted Cracking in Advanced Reactor Coolant Environments |
Author(s) |
Samuel A. Briggs, Peter Beck, Dustin Mangus, Jake Quincey, Xavier Quintana, Guillaume Mignot, Julie D. Tucker |
On-Site Speaker (Planned) |
Samuel A. Briggs |
Abstract Scope |
Stress corrosion cracking, corrosion fatigue, and irradiation-assisted stress corrosion cracking are all complex materials degradation modes that are relatively well-understood in light water reactors. However, these phenomena are not well-studied in advanced reactor environments, where they are likely to manifest in significantly different ways due to higher temperatures and differences in the active corrosion mechanisms in non-aqueous coolant media. To investigate factors governing these behaviors, Oregon State University has recently developed unique test facilities capable of fracture mechanics-based EAC testing in liquid sodium and molten salt environments. These facilities combine some mechanical loading mechanism (e.g., a traditional electronic actuator) with a temperature controlled coolant environment of interest, enabling various environmentally-assisted crack growth tests within wide range of operational environments relevant to most preeminent advanced reactor designs. Results from preliminary slow strain rate tests in molten FLiNaK and U-bend tests in liquid sodium environments will be presented and discussed. |