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In relation to this article, we declare that there is no conflict of interest.
Publication history
Received September 1, 2025
Revised November 3, 2025
Accepted December 7, 2025
Available online June 25, 2026
articles This is an Open-Access article distributed under the terms of the Creative Commons Attribution Non-Commercial License (http://creativecommons.org/licenses/bync/3.0) which permits unrestricted non-commercial use, distribution, and reproduction in any medium, provided the original work is properly cited.
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Forecasting Corrosion Behavior of Structural Materials in Molten Salt Nuclear Reactors

Advanced Fuel Cycle Technology Development Division, Korea Atomic Energy Research Institute 1Department of Nuclear Science and Technology, University of Science and Technology
tkim@kaeri.re.kr
Korean Journal of Chemical Engineering, June 2026, 43(7), 1889-1901(13)
https://doi.org/10.1007/s11814-025-00618-7

Abstract

Molten chloride salts are distinguished by their exceptional ability to withstand high temperatures, surpassing the thermal 

stability of most other salt types. This makes them highly suitable for heat transfer and energy storage applications in areas 

such as concentrated solar power, nuclear energy, and various thermal energy storage technologies. However, corrosion 

in molten chloride environments remains a major challenge. Although extensive research has been conducted to evaluate 

corrosion, a comprehensive method for predicting it in these systems has yet to be developed. This study introduces an 

evaluation framework for assessing corrosion in molten chloride salts based on the predictive capabilities of the Ellingham 

diagram and the oxide–chloride stability diagram. These approaches enable both the prediction of alloy performance and 

a fundamental understanding of corrosion mechanisms in such systems.

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