Deliquescence of Eutectic LiCl-KCl Diluted with NaCl for Interim Waste Salt Storage

Gardner, Levi; Harward, Allison; Howard, Jerry; Fredrickson, Guy L.; Yoo, Tae-Sic; Simpson, Michael; Carlson, Krista

doi:10.1080/00295450.2021.1889923

Deliquescence of Eutectic LiCl-KCl Diluted with NaCl for Interim Waste Salt Storage

Journal Article · Wed Apr 07 00:00:00 EDT 2021 · Nuclear Technology

DOI:https://doi.org/10.1080/00295450.2021.1889923· OSTI ID:1975628

Gardner, Levi ^[1]; Harward, Allison ^[1]; Howard, Jerry ^[1]; ^[2]; ^[2]; Simpson, Michael ^[1]; Carlson, Krista ^[1]

Univ. of Utah, Salt Lake City, UT (United States)
Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Molten eutectic LiCl-KCl salt is a widely used electrolyte for electrorefining uranium from spent nuclear fuel. Due to the hygroscopic nature of this salt, such operations must be performed under controlled atmospheric conditions, and waste salts require careful storage to avoid deliquescence and corrosion of container materials. This study investigated a potential processing path for reducing the degree of deliquescence through dilution to varying extents with NaCl. Here, the hydration behavior of LiCl-KCl salts diluted with NaCl was evaluated in terms of mass gain due to water absorption, degree of deliquescence (including first appearances of standing water), and evidence of corrosion to stainless steel containers in a humid air environment (40°C, 20% relative humidity). In this humid air environment, pure eutectic LiCl-KCl exhibited a 50 mass % increase due to water absorption and showed evidence of standing water after 24 h. Waste salt diluted with NaCl required loadings of 89 mass % NaCl in order to prevent deliquescence and exhibited a 3 mass % increase due to water absorption. After periodic observation for 48 h, standing water was observed near all ingots with the exception of the 89 mass % NaCl samples. Dilution with 89% NaCl was also found to reduce evidence of corrosion when stored in stainless steel crucibles. While dilution with NaCl greatly decreases steady-state hydration, the storage volume is increased ~10× through this procedure.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1975628

Report Number(s):: INL/JOU-23-71178-Rev000

Journal Information:: Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 2 Vol. 208; ISSN 0029-5450

Publisher:: Taylor & FrancisCopyright Statement

Country of Publication:: United States

Language:: English

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