About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments III
|
| Presentation Title |
Effects of Oxygen Contaminated Liquid Sodium on the Degradation of Austenitic Stainless Steels and Inconel 625 |
| Author(s) |
Tolin O. Skov Black, Dev Chidambaram |
| On-Site Speaker (Planned) |
Tolin O. Skov Black |
| Abstract Scope |
GEN IV nuclear reactor designs promise to produce clean energy, while being passively safe and producing minimal waste. Sodium fast reactors (SFRs), one such design, utilize liquid sodium as the coolant; however, due to its reactivity with moisture and oxygen, leaks are considered significantly dangerous. In previous generation SFRs, austenitic steels were used as both the cladding and structural material. However, the search for alternative alloys has recently included high Mo Ni-based alloys such as Inconel 625. In this work, austenitic and Inconel 625 were exposed to varying levels of oxygen polluted static liquid sodium at 550 °C to allow a comparison of the microstructural surface corrosion properties. Described will be the development of the static corrosion testing vessel, mechanism of corrosion, analysis of microstructural surface properties, and estimation of long-term corrosion rates. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Environmental Effects, Iron and Steel |