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Title: Synthesis and characterization of super occluded LiCl-KCl in zeolite-4A as a chloride salt waste form intermediate

Journal Article · · Journal of Nuclear Materials

Here, this paper reports the hygroscopic properties of eutectic LiCl-KCl after absorption into zeolite-4A, up to salt loadings of 75 wt%. Samples of the salt occluded zeolite were hydrated in a humidity chamber at constant temperature and relative humidity for up to 100 h. At up to 45 wt% salt loading, the un-occluded phase of salt consisted primarily of NaCl, which forms when the Na+ ions present in the zeolite framework exchange with Li+ and K+ ions from the eutectic LiCl-KCl. This results in minimal water absorption and corrosion of contacted stainless steel. At greater than 45 wt% salt loading, water absorption and corrosion progressively worsened. The mixture has a significant amount of excess LiCl-KCl, making it highly hygroscopic. This study reveals an option for the intermediate treatment of waste salt from spent nuclear fuel electrorefiners that could facilitate it to be stored in a non-inert atmosphere for extended periods of time before final conversion into a permanent waste form.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Fuel Cycle Research and Development Program
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
2281385
Report Number(s):
INL/JOU--23-71887-Rev000
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 588; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (25)

Characterization of Irradiated Metal Waste from the Pyrometallurgical Treatment of Used EBR-II Fuel journal November 2013
Deliquescence of Eutectic LiCl-KCl Diluted with NaCl for Interim Waste Salt Storage journal April 2021
Two-site equilibrium model for ion exchange between multi-valent cations and zeolite-A in a molten salt journal September 2005
SELECTIVE REDUCTION OF ACTIVE METAL CHLORIDES FROM MOLTEN LiCl-KCl USING LITHIUM DRAWDOWN journal October 2012
Thermal analysis of projected molten salt compositions during FFTF and EBR-II used nuclear fuel processing journal July 2019
Thermo-economic analysis of high-temperature sensible thermal storage with different ternary eutectic alkali and alkaline earth metal chlorides journal December 2018
Thermodynamic calculation of phase diagrams of the 60 common-ion ternary systems containing cations Li, Na, K, Rb, Cs and anions F, Cl, Br, I journal October 1991
The Solubility of Water in Molten Mixtures of LiCl and KCl 1 journal December 1957
Molten salt reactors and electrochemical reprocessing: synthesis and chemical durability of potential waste forms for metal and salt waste streams journal August 2020
Ion exchange kinetics of fission products between molten salt and zeolite-A journal April 2012
Two-Site Equilibrium Model for Ion Exchange between Monovalent Cations and Zeolite-A in a Molten Salt journal July 2003
Development of pyroprocessing technology journal January 1997
A Description of the Ceramic Waste Form Production Process from the Demonstration Phase of the Electrometallurgical Treatment of EBR-II Spent Fuel journal June 2001
Scale Up of Ceramic Waste Forms for Electrorefiner Salts Produced during Spent Fuel Treatment journal November 2015
Optimization of UCl 3 and MgCl 2 separation from molten LiCl-KCl eutectic salt via galvanic drawdown with sacrificial Gd anode journal July 2018
A new inventory tracking method for Mark-V electrorefiner journal June 2019
History and status of spent fuel treatment at the INL Fuel Conditioning Facility journal January 2022
Ceramic-composite waste forms from the electrometallurgical treatment of spent nuclear fuel journal July 1997
Actinide Drawdown From LiCl-KCl Eutectic Salt via Galvanic/chemical Reactions Using Rare Earth Metals journal September 2020
Occlusion and ion exchange in the molten (lithium chloride-potassium chloride-alkali metal chloride) salt + zeolite 4A system with alkali metal chlorides of sodium, rubidium, and cesium journal June 2001
Salt-Zeolite Ion-Exchange Equilibrium Studies for a Complete Set of Fission Products in Molten LiCl-KCl journal September 2010
Fuel Conditioning Facility Electrorefiner Model Predictions versus Measurements journal July 2008
On the reactive occlusion of the (uranium trichloride + lithium chloride + potassium chloride) eutectic salt in zeolite 4A journal March 2000
Equilibrium model for ion exchange between multivalent cations and zeolite-A in a molten salt journal January 2006
Water Sorption/Desorption Characteristics of Eutectic LiCl-KCl Salt-Occluded Zeolites journal September 2022