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Title: Separation of fission products from high-level waste salt systems by partial crystallization: CsCl-NaCl-LiCl-KCl study

Journal Article · · Separation and Purification Technology
 [1];  [2];  [2];  [2];  [3];  [2]
  1. Idaho National Laboratory (INL), Idaho Falls, ID (United States). Glenn T. Seaborg Institute
  2. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
  3. Pennsylvania State Univ., University Park, PA (United States)

Pyroprocessing refers to a series of high-temperature molten-salt processes used to manage and recycle nuclear materials to reduce the waste volume and hazardous environmental impact of the final waste products. Fission products with high halide affinity, including cesium (Cs-137) with a half-life of 30 years, are dissolved into a molten-salt bath. The separation and recovery of cesium can benefit waste-stream minimization because Cs-137—a strong gamma-ray emitter—is a potential source of environmental contamination. This work proposes the recovery of Cs+ from a chloride-salt matrix using a thermally controlled solid-liquid separation. Thermodynamic calculations for the CsCl-NaCl-LiCl-KCl system were performed to predict the partitioning of Cs+ into liquid and solid phases as functions of salt composition and temperature. The selected composition simulated the formulation of high-level salt waste from used fuel treatment. These calculations showed that once the solidus temperature was reached, Cs+ partitions to the liquid phase. According to the thermodynamic calculations, a thermally controlled liquid-solid separation holds the potential to recover up to 92.8 % of the initial cesium chloride. The phase transition temperatures of the sample, including the solidus and liquidus temperatures, were determined using differential scanning calorimetry. The phase composition of the system was studied at various temperatures using high-temperature X-ray diffraction. A laboratory-scale crystallization apparatus was used to melt the sample partially, allowing the collection of the liquid fraction for elemental analysis. All results demonstrated that Cs+ in this system concentrates in the liquid phase and confirmed the viability of recovering CsCl through thermally controlled solid-liquid separation.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC07-05ID14517; DE–AC07–05ID14517
OSTI ID:
2205694
Alternate ID(s):
OSTI ID: 2396902
Journal Information:
Separation and Purification Technology, Vol. 332; ISSN 1383-5866
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (39)

Investigation of Fission Product Transport into Zeolite-A for Pyroprocessing Waste Minimization journal February 2013
Recovery of Alkaline-Earths into Liquid Bi in Ternary LiCl-KCl-SrCl 2 /BaCl 2 Electrolytes at 500 °C journal June 2020
A reactive distillation process for the treatment of LiCl-KCl eutectic waste salt containing rare earth chlorides journal November 2016
Separation of CsCl from a ternary CsCl–LiCl–KCl salt via a melt crystallization technique for pyroprocessing waste minimization journal February 2013
Cesium and strontium recovery from LiCl-KCl eutectic salt using electrolysis with liquid cathode journal October 2022
Current Status of Pyroprocessing Development at KAERI journal January 2013
History and status of spent fuel treatment at the INL Fuel Conditioning Facility journal January 2022
Status of Pyroprocessing Technology Development in Korea journal April 2010
Magnetic zeolite synthesis for efficient removal of cesium in a lab-scale continuous treatment system journal July 2020
State of the Art of Pyroprocessing Technology in Japan journal January 2011
Relationship between zeolite structure and capture capability for radioactive cesium and strontium journal April 2021
SEPARATION OF CsCl FROM LiCl-CsCl MOLTEN SALT BY COLD FINGER MELT CRYSTALLIZATION journal June 2014
SELECTIVE REDUCTION OF ACTIVE METAL CHLORIDES FROM MOLTEN LiCl-KCl USING LITHIUM DRAWDOWN journal October 2012
High-throughput Electrorefining System with Graphite Cathodes and a Bucket-type Deposit Retriever journal January 2012
Candidate waste forms for immobilisation of waste chloride salt from pyroprocessing of spent nuclear fuel journal January 2012
A New Approach to Minimize Pyroprocessing Waste Salts Through a Series of Fission Product Removal Process journal May 2008
ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology journal December 2006
Development of pyroprocessing technology journal January 1997
Separation and Recovery of Uranium Metal from Spent Light Water Reactor Fuel Via Electrolytic Reduction and Electrorefining journal September 2010
Development of Computational Models for the Mark-IV Electrorefiner—Effect of Uranium, Plutonium, and Zirconium Dissolution at the Fuel Basket-Salt Interface journal September 2010
Concentration of Cesium and Strontium Elements Involved in a LiCl Waste Salt by a Melt Crystallization Process journal September 2010
Vitusite glass-ceramics wasteforms for immobilization of lanthanide wastes generated by pyro-processing journal May 2015
Ion exchange kinetics of fission products between molten salt and zeolite-A journal April 2012
Studies in Melt Crystallization journal January 1972
Current Status of Pyrochemical Reprocessing Research in India journal May 2008
Standards, calibration, and guidelines in microcalorimetry. Part 2. Calibration standards for differential scanning calorimetry* (IUPAC Technical Report) journal January 2006
Equilibrium model for ion exchange between multivalent cations and zeolite-A in a molten salt journal January 2006
Removal of Cs+ and Sr2+ ions from simulated radioactive waste solutions using Zeolite-A synthesized from kaolin and their structural stability at high pressures journal January 2021
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
Removal of rare-earth fission products from molten chloride salt used in pyroprocessing by precipitation for consolidation into glass-bonded sodalite waste form journal April 2021
Separation of Cs and Sr from LiCl-KCl eutectic salt via a zone-refining process for pyroprocessing waste salt minimization journal August 2017
Reprocessing spent nuclear fuel using molten carbonates and subsequent precipitation of rare earth fission products using phosphate journal July 2006
Kinetic model for electrorefining, part I: Model development and validation journal January 2014
Minimization of Eutectic Salt Waste from Pyroprocessing by Oxidative Precipitation of Lanthanides journal October 2009
Pyroprocessing Flowsheets for Recycling used Nuclear fuel journal August 2011
Statistical Error Propagation journal April 2001
Immobilization of LiCl-Li2O pyroprocessing salt wastes in chlorosodalite using glass-bonded hydrothermal and salt-occlusion methods journal April 2018
Thermal analysis of projected molten salt compositions during FFTF and EBR-II used nuclear fuel processing journal July 2019