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A GELATIN-FILTRATION HEADEND FOR FUEL REPROCESSING SOLUTIONS FROM SILICON- CONTAINING ALUMINUM ALLOYS

Description: A laboratory study of a gelatin headend process for feed from silicon- containing aluminum fuels and plant salvage solutions is described. The optimum conditions for the gelatin treatment of fuel solutions were to boil a 0.1 to 0.5N nitric acid solution with 100 milligrams of gelatin per liter for 30 minutes. This treatment improved filtration rates and decreased the surface activity of the filtrate for TBP extraction. A number of possible flowsheets for fuel solutions are presented using gelatin treatment and filtration. An adequate treatment was not found for salvage solutions of unknown composition because a gelatin dosage which was satisfactory for all solutions could not be selected. The optimum treatment for a salvage solution which was grossly contaminated with zirconium, soluble and colloidal silica, and dibutyl phosphate was to boil a 1N acid deficient solution with 600 milligrams of gelatin per liter, filter, and use a Hexone extraction system. A silicic colloid in fuel processing solutions was characterized as a surface active material by this study. (auth)
Date: February 1, 1959
Creator: Newby, B.J. & Paige, B.E.
Partner: UNT Libraries Government Documents Department

EUROCHEMIC ASSISTANCE: CHEMICAL TECHNOLOGY DIVISION UNIT OPERATIONS SECTION MONTHLY PROGRESS REPORT, DECEMBER 1958. (SECTIONS 5.0, 6.0, 8.0)

Description: A study of the equiibrium sorption isotherms and rates of U sorption on Dowex 21K is in progress. Data which show the effects of uranium concentration in solution on resin loading are presented Fuel reprocessing experiments are reported in which efforts were made to reduce Cl- in Darex dissolver solution to < 350 ppm for the extraction phase. The best method of Cl/sup -/ reduction appears to be operation with a down draft condenser and an air sparge. A check- out dissolution min in the 6 in. glass dissolver with a prototype APPR fuel element is reported, and data on dissolution time and composition of reacted products are given. Data on filtration rates for Darex solutions expected in large-scale operations are tabulated, and graphs illustrating the effects of pressure drop and filter aids on filtering rates are presented. Tests on washing U from filter cakes indicate that U can be removed to any desired level. Viscosity, density. and boiling points as a function of temperature or pressure were determined for two Darex solvent extraction feed solutions; data are presented grahically, and results of chemical analyses are tabuated. Demonstation runs for Sulfex and Zirflex dejacketing flowsheets were made. Results indicate that parts of the Sulfex flowsheet map have to be changed to prevent core losses from fluoride contamination. Results from the Zirflex demonstration are being compiled. Design of the SRE decanning device was completed and sub mitted to vendors for bids; also the design of a prototype fuel bundle to serve as an inexpensive substitute in chopping and leaching studies is reported. Preliminary shearing studies with the 120 ton hydraulic Manco shear indicate that its usefulness is limited, and criteria for a large shear for spent fuel bundles are being written. Darex-type solvent extraction studies using hexane are reported, and U ...
Date: May 1, 1959
Creator: Shank, E M
Partner: UNT Libraries Government Documents Department

PROCESS DEVELOPMENT QUARTERLY REPORT. PART II. PILOT PLANT WORK

Description: Efficiency of the pilot plant pumper-decanters was greatly improved by the maintenance of interfaccs. The low efficiency of the D-3 pumper-decanter in the plant could be substantially raised by an interface to prevent backmixing. A review of refinery performance, based on a correlation of wash raffinate density with extract uranium saturation showed that high-thorium product resulted from low extract saturation. Tributyl phosphate recovery by hexane stripping of raffinate can be greatly improved through the use of a pamper-decanter in place of the present open column. The pilot plant fluid-bed denitrator has been operated at production rates as high as 500 lb UO/sub 3/hr-sq ft using hlgh feed concentrations. Correlations of previous particle size and heat transfer data are presented. A pilot plant fluid-bed reduction reactor with a tapered internal mandrel has been placed in service. The equipment has performed well in preliminary runs. Equipment to convent low concentration to 38% HF by distillation has been installed. Runs have been made in the green salt reactors in order to simulate the conditions whereby the 38% HF will be utilized. These runs demonstrate the ability to produce high-quality UF/sub 4/ utilizing 38% HF to the Air reactor tube. Laboratory analysis of green salt produced at Port Hope, Canada, indicated the green salt to be approximately comparable a Weldon Spring material, with the exception of hydrogen content, which was about twice the level found in Weldon Spring green salt. Metal from 3300-lb dingots, produced from this green salt by the long-soak technique, had hydrogen levels of 3.9 ppm and 3.4 ppm, which are higher than is normally found in metal produced by the long-soak technique. (auth)
Date: August 1, 1959
Creator: Shepardson, J.U. & Nelson, J.A. eds.
Partner: UNT Libraries Government Documents Department

DIRECT SPECTROPHOTOMETRIC DETERMINATION OF URANIUM IN CYCLOHEXANE SOLUTIONS OF TRI-n-OCTYLPHOSPHINE OXIDE

Description: A method for the direct determination of uranium in a cyclohexane solution of tri-n-octylphosphine oxide (TOPO) is presented. The adduct, UO/sub 2/ Cl/sub 2/ x 2TOPO, that is formed when uranium(VI) is extracted from hydrochloric acid solutions by tri-n-octylphosphine oxide absorbs light in the ultraviolet region. This absorbance is measured at 230 m mu vs. a TOPO-cyclohexane solution that was contacted with hydrochloric acid of the same concentration as that in the test aliquot. The molar absorbance index is 5500. The method is not selective; of the elements that are extracted by TOPO from hydrochloric acid, iron(III), zirconium, molybdenum, tin and thorium, only thorium can be tolerated. (auth)
Date: April 21, 1959
Creator: White, J. C.
Partner: UNT Libraries Government Documents Department

Hexone Extraction-Coulometric Titration of Uranium

Description: Samples containing 5 to 10 mg of uranium were extracted with hexone (methyl isobutyl ketone) and titrated coulometrically in sulfate media. Relative standard deviations of 0.43% for samples containing 5 mg and 0.56% for 10 mg were determined by precision studies. (auth)
Date: June 22, 1959
Creator: Blevins, E. L.
Partner: UNT Libraries Government Documents Department

Some Physical and Chemical Properties of Scandium and the Rare Earths

Description: Conductances, densities, partial molal volumes, solubilities, and transference numbers were measured for scandium chloride, nitrate, and perchlorate. The stability constants of the chelates formed by the rare earths and scandium with ME(l,2-bis- STA2-di(carboxymethyl)aminoethoxy!ethane) and DE(2,2 -bis- STAdi(carboxymethyllaminoldiethyl ether) were measured polarographically. In addition, the stability constants of the scandium chelates of HEDTA (N -hydroxyethyl)-ethylenediamine-N,N,N -triacetic acid), EDTA- (ethylenediamine-N,N,N ,N -tetraacetic acid), DCTA (l,2-diaminocyclohexane-N,N,N ,N -tetraacetic acid), and DE TPA ((carboxymethyl)-bis- (2-di- (carboxymethyl)aminoethyllamine) were also measured. (auth)
Date: July 1, 1959
Creator: Hiller, M. A. & Powell, J. E.
Partner: UNT Libraries Government Documents Department