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Degradation Products of Tributyl Phosphate

Description: Abstract: "A method for determination of dibutyl phosphate in solvent streams containing tributyl phosphate is outlined. The method is based on analysis for total uranium of total phosphate after removal of uranium and phosphate in excess of that present as uranyl dibutyl phosphate. Results on plant solvent samples are presented. Difficulties with precipitation of [...] dibutyl phosphate, when fresh solvents were employed, are discussed. Small amounts of nonphosphate uranium-complexing agents w… more
Date: February 17, 1956
Creator: Ewing, Robert A.; Kiehl, Samuel J. & Bearse, Arthur E.
Partner: UNT Libraries Government Documents Department
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Comparison of Diluents for Tributyl Phosphate

Description: From introduction: This report summarizes a study of the composution and physical properties of a number of hydrocarbon diluents together with some generalizations regarding relations between [vapor pressure, density and viscosity] properties.
Date: October 6, 1950
Creator: Burger, L. L.
Partner: UNT Libraries Government Documents Department
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Physical Properties of Tributylphosphate-Diluent Solutions

Description: In connection with the study of aqueous-tributyIphosphate (TBP) systems, the study of the interactions of various diluents with the TBP has been extended. The diluents used were mineral oil, Amsco 125-90W, dodecane, n-hexane, cyclohexane, benzene, n-octyl bromide, carbon tetrachloride, chloroform and pentachloroethane. The solubility of TBP in water from solutions of these diluents and the solubility of water in the organic phase was determined. For the paraffin hydrocarbons as diluents the … more
Date: September 1, 1953
Creator: Johnson, W. F. & Dillon, R. L.
Partner: UNT Libraries Government Documents Department
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The Solubility of Tributyl Phosphate in Aqueous Solutions

Description: Report describing a study regarding the solubility and related properties of tributyl phosphate (TBP), which has lower solubility in water than most uranium solvents. Pure TBP and TBP in an inert diluent were tested for solubility in water, several nitric acid solutions of varying concentrations, and other solutions typical of process streams. For TBP-diluent-water system tests, equilibrium water content in organic phase was found.
Date: April 2, 1951
Creator: Burger, Leland L. & Forsman, R. C.
Partner: UNT Libraries Government Documents Department
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Alkyl Phosphoric Acids as Extraction Agents for Uranium

Description: The recent interest in tributyl phosphate as an extracting solvent for uranium indicated that consideration of n-butyl phosphoric acid for this application might be of interest if some way could be devised to overcome the manipulation and miscibility difficulties. It was found that if the material was placed in any one of a number of carrier solvents, it had a remarkably strong extractive effect on uranyl ion out of acid solutions without a salting agent present.
Date: January 27, 1950
Creator: Stewart, D. C., (Donald Charles), 1912-1996
Partner: UNT Libraries Government Documents Department
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The Effect of Acidity and Reducing Agents on Ruthenium Solvent Extraction by Tributyl Phosphate in the 25 Process

Description: Results of tracer studies suggest that, in tributyl phosphate extraction processes designed to recover and purify fissionable material, minimum ruthenium extraction should be obtained from feeds at least 2 M in nitric acid or at least 1 M acid-deficient. Ruthenium decontamination was decreased by preheating the feed and increased by pretreatment with reducing agents. A pretreatment using 0.06 M ferrous ion and 0.5 M urea with 1 hr simmering at 85°C should increase ruthenium decontamination abou… more
Date: December 15, 1954
Creator: Flanary, J. R. & Frashier, L. D.
Partner: UNT Libraries Government Documents Department
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Extraction of Americium Nitrate with Tributyl Phosphate

Description: The extraction of americium nitrate with tributyl phosphate has been investigated for aqueous solutions containing sodium nitrate and nitric acid. Americium nitrate is found in the organic phase as free molecules or ions and as the complex (Am(NO3)3. Aqueous solutions containing nitric acid introduce a competitive factor through the formation of the TBP-KNO3 complex in the solvent layer. In addition. americium nitrate is complexed in the aqueous phase by nitric acid.
Date: January 4, 1955
Creator: Walsh, K. A.
Partner: UNT Libraries Government Documents Department
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The Hydrolysis of Tributyl Phosphate Ad Its Effect on the Purex Process

Description: From abstract: "The rate of hydrolysis of TBP and the effect of the hydrolysis products in the Purex Process have been studied. Hydrolytic conditions may be encountered in the process which would lead to formation of dibutyl phosphoric acid, causing significant losses of tetravalent plutonium in stripping. This situation may be easily alleviated by reducing and stripping the plutonium in the trivalent state."
Date: December 13, 1951
Creator: Reilly, V. J. & Lanham, W. B.
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.
Partner: UNT Libraries Government Documents Department
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Recovery of Nitric Acid in the Tributyl Phosphate Process for Uranium Recovery. Part 2.

Description: Report discussing study on recovery of nitric acid in the uranium recovery process. The behavior of chloride ions and tributyl phophate is noted, and the quality of recycled nitric acid was tested. Stainless steel in the nitric acid recovery system was evaluated for corrosion.
Date: May 29, 1950
Creator: Wagner, R. M. & Groot, C.
Partner: UNT Libraries Government Documents Department
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Preparation and Properties of RAF Solutions : Low Acid TBP Flowsheets HW Number 4 and HW Number 5

Description: This report follows work with the purposes of determining the minimum amount of nitric acid required to dissolve slurries of stored metal waste, determining the stability of such metastable solutions as a function of their chemical compositions - primarily acidity - versus time and temperature, and to define a feed suitable for a low-acid TBP process flowsheet, and to indicate the range of variations in composition which can be tolerated for plant operation.
Date: July 25, 1950
Creator: Maness, R. F. & Harmon, M. K.
Partner: UNT Libraries Government Documents Department
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The Densities of Tributyl Phosphate - Carbon Tetrachloride Solutions Containing Uranium and Nitric Acid

Description: The following report provides the analysis of a large number of unreported data--taken during a study described in report HW-15230--containing density values obtained for solutions of uranium and nitric acid in tributyl phosphate-carbon tetrachloride solutions.
Date: December 20, 1949
Creator: Moore, Robert Lee
Partner: UNT Libraries Government Documents Department
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TBP Stripping in Bubble-Cap Column and Concomitant Product Evaporation

Description: A study was conducted to demonstrate the stripping and evaporation steps in a Purex-type uranium recovery process and to ascertain the operating behavior of the equipment under a range of conditions. The factors considered were control, effectiveness, and reliability of equipment and optimum feed point. Experimental procedures are described, and recommendations for equipment modifications are included. (J.R.D.)
Date: March 18, 1957
Creator: Long, J. T.
Partner: UNT Libraries Government Documents Department
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Continuous Solvent Recovery Process Using Pulse Contacting Column

Description: From abstract: "This report presents the progress in the laboratory development of a continuous solvent recovery process for the tributyl phosphate-diluent mixture used in the Purex Process. Investigations were made with 1/2" diameter pulse columns, using a nine foot sodium carbonate contacting column and a four foot water wash column."
Date: April 1, 1952
Creator: Ellison, C. V. & Land, J. F.
Partner: UNT Libraries Government Documents Department
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Monex Process: Terminal Report

Description: Chemical and engineering data were obtained for the feed digestion system and the extraction-scrub step of the Monex tributyl phosphate solvent-extraction process for recovering thorium and uranium from nitric acid-digested unclarified monasite sludge. Tests of the recommended conditions in a 2-in.-dia pulsed column demonstrated that thorium losses were approximately 1.2% and uranium losses, 1.5%. The flowsheet is workable but is not necessarily optimum.
Date: January 31, 1958
Creator: McNamee, R. J. & Wischow, R. P.
Partner: UNT Libraries Government Documents Department
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Distribution of Uranyl Nitrate Between Al(NO3)3 and Tributyl Phosphate

Description: From abstract: "The distribution of uranyl nitrate was measured from aluminum nitrate and nitric acid solutions into diluted tri-n-butyl phosphate. This information is useful for designing solvent extraction processes for recovery of uranium from aluminum nitrate or nitric acid solutions."
Date: March 1958
Creator: Ames, Donald P. & Karraker, David G.
Partner: UNT Libraries Government Documents Department
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Effect of Solvent Degradation on the Purex Process

Description: From abstract: "The combined attack of HNO3 and HNO2 on tributyl phosphate - kerosene solvent used in the Purex process produces degradation products that cause abnormal quantities of zirconium to be extracted along with the plutonium and uranium and thus limits the decontamination."
Date: May 1958
Creator: Siddall, Thomas H., III; Wallace, Richard M. & Prout, W. E.
Partner: UNT Libraries Government Documents Department
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Acid Formation in the Radiolysis of Phosphorus Esters

Description: The radiolytic decomposition of tributyl phosphate has been show by burr to product gases, acids, and polymers. the acids that are formed can limit the usefulness of tributyl phosphate for the processing of radioactive materials. The study of acid formation on radiolysis therefor becomes important to us for the understanding of the mechanism of acid formation, the influence of added materials and the effect of the structure of organo- phosphorous compounds. Samples of purified esters have been … more
Date: April 3, 1957
Creator: Baldwin, W. H.
Partner: UNT Libraries Government Documents Department
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Evaluation of Tributyl Phosphate in Jet Mixing Columns as a Solvent for Uranium Extraction From Slurry-Type Ore Feeds

Description: Technical report outlining the physical operability of 30% tributyl phosphate in a hydrocarbon dilutent for the extraction of uranium from more feed slurries. Operability had been satisfactorily demonstrated in jet mixing columns at the pilot plant of the Mallinckrodt Chemical Works. [From Abstract]
Date: December 7, 1950
Creator: Runion, T. C. & Yeager, J. H.
Partner: UNT Libraries Government Documents Department
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FMPC Solvent Treatment Area - Process Design

Description: This memorandum presents the process design for the solvent reast area of the Feed Materials Production Center. The purpose ofthe transmittal is to provide the basis for the detailed mechanical design and layout of this section of the refinery. Drawings, flowsheets, and specifications are included.
Date: July 6, 1951
Creator: Pfeiffer, Carl & Maerker, John B.
Partner: UNT Libraries Government Documents Department
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