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Title: An Advanced TALSPEAK Concept for Separating Minor Actinides. Part 2. Flowsheet Test with Actinide-spiked Simulant

Journal Article · · Solvent Extraction and Ion Exchange
ORCiD logo [1]; ORCiD logo [2];  [1]; ORCiD logo [1];  [1];  [1];  [3];  [4];  [1]; ORCiD logo [1]
  1. Forschungszentrum Jülich GmbH, Institut für Energie – und Klimaforschung – Nukleare Entsorgung und Reaktorsicherheit (IEK-6), Jülich, Germany
  2. Nuclear Science and Engineering Group, Pacific Northwest National Laboratory, Richland, DC, USA
  3. Aqueous Separations and Radiochemistry Department, Idaho National Laboratory, Idaho Falls, ID, USA
  4. Karlsruhe Institute of Technology (KIT), Institute for Nuclear Waste Disposal (INE), Karlsruhe, Germany

A solvent extraction system has been developed for separating trivalent actinides from lanthanides. This “Advanced TALSPEAK” system uses 2-ethylhexylphosphonic acid mono-2-ethylhexyl ester to extract the lanthanides into a n-dodecane-based solvent phase, while the actinides are retained in a citrate-buffered aqueous phase by complexation to N-(2-hydroxyethyl)ethylenediamine-N,N',N'-triacetic acid. Batch distribution measurements indicate that the separation of americium from the light lanthanides decreases as the pH decreases. For example, the separation factor between La and Am increases from 2.5 at pH 2.0 to 19.3 at pH 3.0. However, previous investigations indicated that the extraction rates for the heavier lanthanides decrease with increasing pH. So, a balance between these two competing effects is required. An aqueous phase in which the pH was set at 2.6 was chosen for further process development because this offered optimal separation, with a minimum separation factor of ~8.4, based on the separation between La and Am. Centrifugal contactor single-stage efficiencies were measured to characterize the performance of the system under flow conditions.

Research Organization:
Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC05-76RL01830
OSTI ID:
1406777
Report Number(s):
PNNL-SA-122678; AF5805010
Journal Information:
Solvent Extraction and Ion Exchange, Vol. 35, Issue 6; ISSN 0736-6299
Publisher:
Taylor and Francis
Country of Publication:
United States
Language:
English

References (26)

An Advanced TALSPEAK Concept for Separating Minor Actinides. Part 1. Process Optimization and Flowsheet Development journal August 2017
Minor actinide separation in the reprocessing of spent nuclear fuels book January 2015
Minor actinide separations in the reprocessing of spent nuclear fuels book April 2015
Process Development and Laboratory-scale Demonstration of a regular-SANEX Process Using C5-BPP (2,6-Bis(5-(2,2-dimethylpropyl)-1 H -pyrazol-3-yl)pyridine) journal June 2015
Actinide Partitioning—A Review journal May 2001
The Chemistry of TALSPEAK: A Review of the Science journal December 2014
Demonstration of a TODGA‐Based Continuous Counter‐Current Extraction Process for the Partitioning of Actinides from a Simulated PUREX Raffinate, Part II: Centrifugal Contactor Runs journal January 2008
The Truex Process and the Management of Liquid Tru Uwaste journal October 1988
Main Results of the French Program on Partitioning of Minor Actinides, a Significant Improvement Towards Nuclear Waste Reduction journal January 2012
Time-Dependent Implementation of Argonne’s Model for Universal Solvent Extraction journal September 2012
Combining CMPO and HEH[EHP] for Separating Trivalent Lanthanides from the Transuranic Elements journal October 2013
Demonstration of the LUCA process for the separation of americium(III) from curium(III), californium(III), and lanthanides(III) in acidic solution using a synergistic mixture of bis(chlorophenyl)dithiophosphinic acid and tris(2-ethylhexyl)phosphate journal January 2010
The TRUSPEAK Concept: Combining CMPO and HDEHP for Separating Trivalent Lanthanides from the Transuranic Elements journal May 2013
Solvent Extraction and Fluorescence Spectroscopic Investigation of the Selective Am(III) Complexation with TS-BTPhen journal January 2016
Direct Selective Extraction of Actinides (III) from PUREX Raffinate using a Mixture of CyMe 4 BTBP and TODGA as 1-cycle SANEX Solvent Part III: Demonstration of a Laboratory-Scale Counter-Current Centrifugal Contactor Process journal March 2013
Progress towards the Full Recovery of Neptunium in an Advanced PUREX Process journal July 2013
The role of carboxylic acids in TALSQuEAK separations journal August 2012
Recent Advances in the Development and Application of Annular Centrifugal Contactors in the Nuclear Industry journal December 2013
Review: Solvent Systems Combining Neutral and Acidic Extractants for Separating Trivalent Lanthanides from the Transuranic Elements journal April 2010
Alternatives to HDEHP and DTPA for Simplified TALSPEAK Separations journal June 2011
THE TRUEX PROCESS - A PROCESS FOR THE EXTRACTION OF THE TKANSURANIC ELEMENTS EROM NITRIC AC In WASTES UTILIZING MODIFIED PUREX SOLVENT* journal February 1985
Advanced TALSPEAK Separations Using a Malonate Buffer System journal February 2015
An Advanced TALSPEAK Concept Using 2-Ethylhexylphosphonic Acid Mono-2-Ethylhexyl Ester as the Extractant journal December 2014
Recent advances on the chemistry of solvent extraction applied to the reprocessing of spent nuclear fuels and radioactive wastes journal January 2004
Impact of partitioning and transmutation on the high level waste management journal September 2011
Review Article: A Review of the Development and Operational Characteristics of the TALSPEAK Process journal October 2007