Nuclear Engineering and Technology (Mar 2024)

Thermal dehydration tests of FLiNaK salt for thermal-hydraulic experiments

  • Shuai Che,
  • Sheng Zhang,
  • Adam Burak,
  • Xiaodong Sun

Journal volume & issue
Vol. 56, no. 3
pp. 1091 – 1099

Abstract

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Fluoride-salt-cooled High-temperature Reactor (FHR) is a promising nuclear reactor technology. Among many challenges presented by the molten fluoride salts is the corrosion of salt-facing structural components. Higher moisture contents, in the FLiNaK (LiF-NaF-KF, 46.5–11.5-42 mol%) salt, aggravate intergranular corrosion and pitting for the given alloys. Therefore, several thermal dehydration tests of FLiNaK salt were performed with a batch size suitable for thermal-hydraulic experiments. Thermogravimetric Analysis (TGA) was performed for the three constituent fluoride salts individually. Preliminary thermal dehydration plans were then proposed for NaF and KF salts based on the TGA curves. However, the dehydration process may not be required for LiF since its low mass loss (500 °C) were necessary to remove a significant amount of moisture (>1 wt%) from NaF salt, while relatively low temperatures (around 300 °C) with a long holding time (>10 h) were sufficient to remove most of the moisture from KF salt.

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