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Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process : Continuing Development Studies

Description: This report summarizes the work done to date on the application of the TRUEX solvent extraction process for removing and separately recovering plutonium and americium from a nitric acid waste solution containing these elements, uranium, and a complement of inert metal ions. This simulated waste stream is typical of a raffinate from a tributyl phosphate (TBP)-based solvent extraction process for removing uranium and plutonium from dissolved plutonium-containing metallurgical scrap. The TRUEX pro… more
Date: September 1985
Creator: Leonard, R. A.; Vandegrift, G. F.; Kalina, D. G.; Fischer, D. F.; Bane, R. W.; Burris, L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transuranic Decontamination of Nitric Acid Solutions by the Truex Solvent Extraction Process: Preliminary Development Studies

Description: This report summarizes the work that has been performed to date at Argonne National Laboratory on the development of the TRUEX process, a solvent extraction process employing a bifunctional organophosphorous reagent in a PUREX process solverc (tributyl phosphate-normal paraffinic hydrocarbons). The purpose of this extraction process is to separate and concentrate transuranic (TRU) elements from nuclear waste.
Date: July 1984
Creator: Vandegrift, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Separation of Zirconium & Hafnium : Proposal for Construction & Operation of Zirconium Production Plant

Description: Abstract: A re-evaluation of the cost of producing essentially hafnium free zirconium as zirconium oxide at a rate of 150,000-200,000 pounds zirconium per year by solvent extraction of the metal thiocyanates in a permanent plant has been made. Using part of the present temporary facilities, the cost, with five year amortization of the plant, will be $3.15 per pound zirconium. A by-product of the mixed oxides of hafnium and zirconium, having at least fifty percent hafnium and perhaps as high as … more
Date: November 17, 1955
Creator: Googin, J. M. & Strasser, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sludge Technology Assessment

Description: This document is intended to (1) identify separation technologies which are being considered for sludge treatment at various DOE sites, (2) define the current state of sludge treatment technology, (3) identify what research and development is required, (4) identify current research programs within either DOE or academia developing sludge treatment technology, and (5) identify commercial separation technologies which may be applicable. Due to the limited scope of this document, technical evaluat… more
Date: December 1994
Creator: Krause, T. R.; Cunnane, J. C. & Helt, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Magnetically Assisted Chemical Separation (MACS) Process : Preparation and Optimization of Particles for Removal of Transuranic Elements

Description: This report describes the development of a separation process for TRU elements from various high-level waste streams.
Date: September 1994
Creator: Nuñez, Luis; Kaminski, M.; Bradley, C.; Buchholz, B. A.; Landsberger, S.; Aase, S. B. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Actinide Recovery Using Aqueous Biphasic Extraction: Initial Developmental Studies

Description: Aqueous biphasic extraction systems are being developed to treat radioactive wastes. The separation technique involves the selective partitioning of either solutes or colloid-size particles between two scible aqueous phases. Wet grinding of plutonium residues to an average particle size of one micron will be used to liberate the plutonium from the bulk of the particle matrix. The goal is to produce a plutonium concentrate that will integrate with existing and developing chemical recovery proces… more
Date: August 1992
Creator: Chaiko, David J.; Mensah-Biney, R.; Mertz, C. J. & Rollins, A. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Vibration Model for Centrifugal Contactors

Description: Using the transfer matrix method, we created the Excel worksheet "Beam" for analyzing vibrations in centrifugal contactors. With this worksheet, a user can calculate the first natural frequency of the motor/rotor system for a centrifugal contactor. We determined a typical value for the bearing stiffness (k(sub B)) of a motor after measuring the k(sub B) value for three different motors. The k(sub B) value is an important parameter in this model, but it is not normally available for motors. The … more
Date: November 1992
Creator: Leonard, R. A.; Wasserman, M. O. & Wygmans, D. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of Actinides from TBP-Na₂CO₃ Scrub-Waste Solutions: the ARALEX Process

Description: A flow-sheet for the recovery of actinides from TBP-Na2CO3scrub-waste solutions has been developed, based on batch extraction data, and tested, using laboratory-scale countercurrent extraction techniques. The process, called the ARALEX process, uses 2-ethyl-1-hexanol (2-EHOH) to extract the TBP degradation products (HDBP and H/sub 2/MBP) from acidified Na2CO3scrub waste leaving the actinides in the aqueous phase. Dibutyl and monobutyl phosphoric acids are attached to the 2-EHOH molecules throug… more
Date: August 1979
Creator: Horwitz, E. P.; Bloomquist, C. A. A.; Mason, G. W.; Leonard, R. A. & Ziegler, A. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Di-n-Amyl-n-Amylphosphonate and Tricaprylmethylammonium Nitrate as Potential Extractants for Reprocessing Th-U Fuels

Description: Both 2F di-n-amyl-n-amylphosphonate in n-dodecane (DA(AP)-DD) and 0.77F tricaprylmethylammonium nitrate in Aromatic 100 (TCMA.NO/sub 3/-AR100) extract uranium and thorium into relatively concentrated organic solutions. Countercurrent-flow tests with each extractant have demonstrated effective uranium-thorium separations by selective stripping from the organic phase. Both extractants offer advantageous alternatives to tributylphosphate (Thorex) in reprocessing irradiated mixed ThO2-UO2 fuels. Fo… more
Date: September 1979
Creator: Diamond, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TRUEX Hot Demonstration

Description: In FY 1987, a program was initiated to demonstrate technology for recovering transuranic (TRU) elements from defense wastes. This hot demonstration was to be carried out with solution from the dissolution of irradiated fuels. This recovery would be accomplished with both PUREX and TRUEX solvent extraction processes. Work planned for this program included preparation of a shielded-cell facility for the receipt and storage of spent fuel from commercial power reactors, dissolution of this fuel, op… more
Date: April 1990
Creator: Chamberlain, D. B.; Leonard, R. A.; Hoh, J. C.; Gay, E. C.; Kalina, D. G. & Vandegrift, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Review of Supercritical Fluid Extraction

Description: Forward: The purpose of this report is to summarize the results obtained from a brief investigation of supercritical fluid extraction principles and applications. This study was one portion of a project funded by the U.S. Department of Energy, Office of Fossil Energy, contract nuriber DE-AI01076PR06010, in response to a preliminary proposal submitted by the authors. This report sometimes uses company trade naries to identify processes and patent holders. This usage implies no endorsement by HBS… more
Date: December 1983
Creator: Ely, James F. & Baker, Jolene K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A New Anionic Solvent Extraction Technique

Description: From abstract: "The extraction of acids with long-chain amines is described. Preliminary results on the extraction of the amine salts of polonium, plutonium and uranium are given."
Date: July 17, 1952
Creator: Moore, F. L.; Kelley, M. T. & Susano, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Alternate Solvents for Diethyl Ether in the Extraction of Uranium From Mallinckrodt Type Ore Feeds

Description: Technical report evaluating solvents for use in the extraction of uranium from Mallinckrodt type ore feeds. Re-evaluates the Mallinckrodt process in the light of the more recent solvent extraction development that has been carried out at various AEC sites.
Date: November 6, 1950
Creator: Runion, T. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section C Monthly Progress Report - September 1959

Description: Progress report on recovery of uranium from amines, amine extraction of Pu (III) nitrate, plutonium (IV) nitrate extraction with phenylphosphonate esters, effect of salt type on rare earth extraction from nitrate solutions by neutral organophosphorus reagents, effect of reagent structure on rare earth extraction from nitrate solutions, neptunium recovery from laboratory salvage, examination of process irradiated TBP and reagent clean-up methods, fission product recovery, activities in solvent e… more
Date: October 20, 1959
Creator: Brown, K. B.; Allen, K. A.; Blake, C. A.; Coleman, C. F.; Crouse, D. J.; Weaver, B. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of First Cycle Scrub Ration Reduction on Decontamination in the "25" Process

Description: The scrub flow ratio in the first cycle of the Hexone solvent extraction process for the recovery and decontamination of uranium from aluminum-uranium alloy fuels has been reduced by a factor of 10. A minimum flow ration of scrub : feed : extractant of 1: 79 : 67 has been plant-tested. Uranium losses were unaffected, and overall fission product decontamination for three cycles was changed only slighty
Date: unknown
Creator: Schilling, F.-P. (Frank-Peter)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Review and Evaluation of Extractants for Strontium Removal Using Magnetically Assisted Chemical Separation

Description: A literature review on extractants for strontium removal was initially performed at Northern Illinois University to assess their potential in magnetically assisted chemical separation. A series of potential strontium extractants was systematically evaluated there using radioanalytical methods. Initial experiments were designed to test the uptake of strontium from nitric acid using several samples of magnetic extractant particles that were coated with various crown ether ligands. High partition … more
Date: November 1995
Creator: Bauer, C. B.; Rogers, R. D.; Nuñez, Luis; Ziemer, M. D.; Pleune, T. T. & Vandegrift, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aqueous Biphasic Extraction of Uranium and Thorium from Contaminated Soils : Final Report

Description: The aqueous biphasic extraction (ABE) process for soil decontamination involves the selective partitioning of solutes and fine particulates between two immiscible aqueous phases. The biphase system is generated by the appropriate combination of a water-soluble polymer (e.g., polyethylene glycol) with an inorganic salt (e.g., sodium carbonate). Selective partitioning results in 99 to 99.5% of the soil being recovered in the cleaned-soil fraction, while only 0.5 to 1% is recovered in the contamin… more
Date: July 1995
Creator: Chaiko, David J.; Gartelmann, J.; Henriksen, J. L.; Krause, T. R.; Deepak; Vojta, Y. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Extraction of Long-Lived Radionuclides from Caustic Hanford Tank Waste Supernatants

Description: A series of polymer-based extraction systems, based on the use of polyethylene glycols (PEGs) or polypropylene glycols (PPGs), was demonstrated to be capable of selective extraction and recovery of long-lived radionuclides, such as Tc-99 and I-129, from Hanford SY-101 tank waste, neutralized current acid waste, and single-shell tank waste simulants. During the extraction process, anionic species like TcO₄⁻ and I⁻ are selectively transferred to the less dense PEG-rich aqueous phase. The partitio… more
Date: July 1995
Creator: Chaiko, David J.; Mertz, C. J.; Vojta, Y.; Henriksen, J. L.; Neff, R. & Takeuchi, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Minimum Additive Waste Stabilization (MAWS), Phase 1: Soil Washing Final Report

Description: As a result of the U.S. Department of Energy's environmental restoration and technology development activities, GTS Duratek, Inc., and its subcontractors have demonstrated an integrated thermal waste treatment system at Fernald, OH, as part the Minimum Additive Waste Stabilization (MAWS) Program. Specifically, MAWS integrates soil washing, vitrification of mixed waste streams, and ion exchange to recycle and remediate process water to achieve, through a synergistic effect, a reduction in waste … more
Date: August 1995
Creator: Argonne National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Solvent Extraction

Description: Report discussing methods and theories of solvent extraction. Factors that influence solvent extraction, such as the distribution coefficient, relative solubility, and physical properties of the solvent, are discussed as well.
Date: July 18, 1947
Creator: Smellie, Robert H., Jr. & Krause, D. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Acid Processes for the Extraction of Alumina

Description: Report presenting the Bureau of Mines' investigation into acid processes of extracting alumina. The paper discusses the sulphuric acid processes and other work with hydrochloric and nitric acids so that the comparative advantages can be appreciated.
Date: 1927
Creator: Tilley, George S.; Millar, Russell Ward & Ralston, Oliver Caldwell
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Separation of Iron by Liquid-Liquid Column Extraction

Description: From abstract: "Iron(III) can be separated from many elements by extraction from 6 to ͟8M hydrochloric acid. The extraction is carried out by passing the aqueous hydrochloric acid solution through a column packed with 2-octanone adsorbed onto a poly-fluorocarbon resin. Fluoride, phosphate, sulfate or citrate cause no interference. Traces if iron(III) can be separated quantitatively from large amounts of copper(II) or zinc(II); traces of titanium(IV) can be separated from large amounts of iron(II… more
Date: March 21, 1962
Creator: Fritz, James S. (James Sherwood), 1924- & Hedrick, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Laboratory Development of a Tributyl Phosphate Solvent Extraction Process for Processing 20% Enriched Uranium Alloy Fuel

Description: Report containing a preliminary chemical flowsheet "for the preparation of feed and two solvent extraction cycles for the processing of silicon-containing aluminum-uranium alloy, 20% enriched, fuel elements" (p. 2).
Date: 1961
Creator: Goode, J. H. & Flanary, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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