About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
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Mechanical Behavior of Nuclear Reactor Materials and Components III
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Presentation Title |
Investigating Environmentally-Assisted Cracking in 316 Stainless Steel U-Bend Specimens Exposed to Liquid Sodium |
Author(s) |
Dustin Mangus, Xavier Quintana, Guillaume Mignot, Wade Marcum, Julie Tucker, Samuel Briggs |
On-Site Speaker (Planned) |
Dustin Mangus |
Abstract Scope |
The combination of mechanical and environmental stressors tends to accelerate degradation of structural materials in nuclear reactors and other extreme environments, which can be life-limiting in these systems. Despite this, these phenomena are not well-studied for advanced reactor systems, such as sodium fast reactors. Oregon State University has recently developed the Glovebox for Experimental Liquid Sodium (GELS) facility to simulate prototypical SFR environments to enable for a wide array of materials testing. In initial tests, 316 stainless steel U-bend specimens have been immersed in an oxygen-controlled sodium environment to assess the effects corrosion and liquid metal embrittlement on the strained samples. The capabilities of OSU’s GELS facility and details of efforts to develop sodium prewetting capabilities will be highlighted. In addition, post-mortem characterization of as-received and immersed U-bend samples will be analyzed to evaluate the microstructural evolution and performance of strained austenitic stainless steels in SFR environments. |
Proceedings Inclusion? |
Planned: |
Keywords |
Iron and Steel, Nuclear Materials, Environmental Effects |