| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
2022 Technical Division Student Poster Contest
|
| Presentation Title |
SPG-35: Discovering the Corrosion Mechanism of Chromium in High-temperature LiF-NaF-KF Molten Salts for Gen-IV Molten Salt Reactor Applications |
| Author(s) |
Ho Lun Chan, Elena Romanovskaia, Minsung Hong, Peter Hosemann, John Scully |
| On-Site Speaker (Planned) |
Ho Lun Chan |
| Abstract Scope |
Chromium, a ubiquitous and powerful alloying element possible structural materials in advanced nuclear reactor alloys, is susceptible to selective dissolution in molten fluoride salts in the presence of hydrofluoric acid, which is formed by the adsorption and reaction of moisture impurity in molten fluorides. In this project, the thermodynamic stability of Cr in the Cr0, Cr2+ and Cr3+ oxidation states considering various F- ion coordination was investigated in molten LiF-NaF-KF (FLiNaK) eutectic salt. Corrosion was a strong function of thermodynamic and kinetic factors. Potential-fluoride ion activity diagrams were constructed to predict the F- stability region where spontaneous corrosion of Cr occurs. Electrochemical methods were utilized to relate the interface corrosion kinetics to the predicted stability region. The present work aims to identify key thermodynamic and kinetic factors that are significant to the chromium corrosion for molten salt nuclear reactor applications. |
| Proceedings Inclusion? |
Undecided |
| Keywords |
High-Temperature Materials, Nuclear Materials, Other |