| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
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Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
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| Presentation Title |
Corrosion Behavior of Pre- and Post-irradiated Metals in Molten Chloride Salts |
| Author(s) |
Robert O. Gentile, Michael Woods, Laura Hawkins, Ruchi Gakhar, Trishelle Copeland-Johnson, Daniel Murray, Zhihan Hu, Lin Shao, Lingfeng He |
| On-Site Speaker (Planned) |
Robert O. Gentile |
| Abstract Scope |
Molten Salt Reactors (MSRs) are one of several next-generation advanced nuclear reactors to supply the US power grid. The corrosion of reactor structural materials has been one key challenge faced in the development of MSRs. To comprehend structural alloys’ behavior in MSR extreme environments, it is important to understand the fundamental corrosion mechanisms of simple metals in simulated corrosive environments. In this work, we study corrosion mechanisms for pre- and post-irradiated metals. Pure Ni and Ni20Cr model alloys are exposed to NaCl-MgCl2 molten chloride salt at 700 °C, before and after 2 MeV proton irradiation. Multimodal characterization techniques like scanning electron microscopy, electron backscatter diffraction, (scanning) transmission electron microscopy, energy-dispersive X-ray spectroscopy, electron energy loss spectroscopy, and electron diffraction are employed to characterize the microstructure and defects of the model alloys in these extreme conditions. This study will demonstrate the effect of irradiation-induced defects on the molten salt corrosion results. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, |