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Static exposure tests of pre-oxidized stainless steel and carburized chromium were conducted in the molten fluoride salt, LiF-NaF-KF (46.5-11.5-42 mol %), FLiNaK to simulate the corrosion environment typical of some advanced nuclear reaction concepts.
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Several Generation IV nuclear reactor concepts feature molten fluoride salt coolants. Corrosion of alloys in molten fluorides remains a challenge. Static exposure tests of nickel-based alloys and austenitic stainless steels were conducted in the molten fluoride salt known as FLiNaK.
Accurate representations of the thermochemistry and phase equilibria of relevant molten salt constituents and their aggregate behavior are critical to the development, design, operation, and licensing of any molten salt reactor (MSR). This need is currently being addressed by the creation of a dedicated, high quality/validated MSR thermochemical database, the Molten Salt Thermal Properties Database-Thermochemical (MSTDB-TC). MSTDB-TC is being populated with prioritized models and values for vapor species, and liquid and crystalline phases of chloride and fluoride fuel and coolant salts with relevant fission product and transuranic elements, and more recently with corrosion-relevant systems with chromium, iron, and nickel. Multi-cation crystalline and melt solution models are being incorporated, including newly developed relations as necessary, to obtain real system behavior.