About this Abstract |
Meeting |
2024 TMS Annual Meeting & Exhibition
|
Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
|
Presentation Title |
Corrosion Mechanism of Cold Worked 316 Stainless Steel in Molten FLiNaK Salt |
Author(s) |
Minsung Hong, Shmuel Samuha, Peter Hosemann |
On-Site Speaker (Planned) |
Shmuel Samuha |
Abstract Scope |
Molten FLiNaK salt is a potential coolant for next-generation molten salt nuclear reactors. Due to its corrosive impact on nuclear power components, it is vital to understand the dominant corrosion mechanisms associated with it before incorporating it into nuclear reactors. Therefore, the current research aims at developing a comprehensive understanding of the corrosion behavior of austenitic 316 stainless steel, a commonly used structural material in the nuclear industry. As manufacturing processes result in chemical and microstructural changes, current research focuses on the effects of cold-working on corrosion behavior. Plastic deformation was introduced via cold-forging (5 to 50%) and was followed by immersion in molten FLiNaK salt for 48 hours at 700 °C. A multi-scale correlative investigation was conducted, including mechanical testing and in-depth electron crystallography characterization before and following immersion tests. Corrosion behavior was then explained in the context of fundamental characteristics, including defects’ characteristics, elemental composition, and phase content. |
Proceedings Inclusion? |
Planned: |
Keywords |
Characterization, Environmental Effects, Nuclear Materials |