About this Abstract |
Meeting |
2022 TMS Annual Meeting & Exhibition
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Symposium
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Materials and Chemistry for Molten Salt Systems
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Presentation Title |
The Corrosion of Severely Plastically Deformed SS316 in LiCl-Li<sub>2</sub>O at 650 °C |
Author(s) |
Jeremy T. Moon, Andrew Hoffman, Haiming Wen, Dev Chidambaram |
On-Site Speaker (Planned) |
Jeremy T. Moon |
Abstract Scope |
The corrosion of SS316/SS316L exposed to LiCl-Li<sub>2</sub>O molten salt with dissolved Li metal during the electrolytic reduction of commercial oxide nuclear fuel is a complex process mediated by the formation and dissolution of precipitates in grain boundaries and in the bulk material as well as transport of the electrolyte through grain boundaries. We have previously observed that low-angle and twin grain boundaries experience less severe intergranular attack. In the present work, severely plastically deformed (SPD) SS316 fabricated using equal channel angular pressing (ECAP) and high-pressure torsion (HPT) were exposed to LiCl-Li<sub>2</sub>O (1 wt.%) at 650 °C for 100 hours in order to observe the effects of ultrafine and nanocrystalline grain sizes on the corrosion of SS316. Results of characterization studies of the exposed surface of SPD SS316 using scanning electron microscopy, X-ray energy dispersive spectroscopy, X-ray diffraction, and X-ray photoelectron spectroscopy will be presented and compared to traditionally manufactured SS316. |
Proceedings Inclusion? |
Planned: |
Keywords |
Pyrometallurgy, Nuclear Materials, Characterization |