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Corrosion-Resistant Materials for Hydrofluoric Acid : Progress Report

Description: Introduction: Among the many corrosion problems encountered in the production of uranium tetrafluoride and uranium metal from ores and concentrates, some of the most serious occur where hydrofluoric acid must be handled.
Date: June 15, 1953
Creator: Pray, H. A.; Fink, F. W.; Friedl, B. E. & Braun, W. J.
Partner: UNT Libraries Government Documents Department
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The Determination of Rare Earths in Thorium

Description: Abstract: "A quantitative method for the determination of individual rare earths in thorium down to a level of 0.05 ppm, is described. The procedure consists of a chromatographic cellulose-columns separation followed by a solution-type spectrographic determination. Values are given for the recovery of a number of rare earths using this combined procedure."
Date: May 15, 1952
Creator: Center, E. J.; Henry, W. M. & Householder, R. D.
Partner: UNT Libraries Government Documents Department
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Zirconium Pilot Plant Research and Development Progress Report

Description: The following report studies the effect of flow rates and deposition pressure on the zirconium deposition in the zirconium pilot plant with the use of a Hilco oil purifier for the vacuum pumps that permitted studies to continue through the month.
Date: November 20, 1951
Creator: Dryden, C. E.; Accountius, O. E.; Black, D. G.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
Partner: UNT Libraries Government Documents Department
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Identification of Reaction Products Formed During Magnesium Reduction of Uranium Tetrafluoride: Report

Description: Abstract: "This report describes the results of X-ray diffraction examination of reaction products from a series of experiments performed by Mallinckrodt Chemical Works as an acid in understanding the process of bomb reduction of UF4. UF4 is initially reduced to UF3 by magnesium at 560 C., and subsequently to metal at 600 C. MgF2 from the initial reaction forms a coating on the magnesium which retards the final spontaneous reaction."
Date: May 15, 1953
Creator: Schwartz, C. M. & Vaughan, D. A.
Partner: UNT Libraries Government Documents Department
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Estimated Manufacturing Costs for the Recovery of Thorium and Uranium from Monazite Sand

Description: Abstract: "Costs have been estimated for the production of uranium and pure thorium from monasite concentrates by a process involving (1) reaction of monasite with caustic soda, (2) dissolution of the hydrous oxides in hydrochloric acid, (3) separation from the bulk of the rare earths by hydroxide precipitation of thorium and uranium, and (4) purification by solvent extraction."
Date: September 15, 1950
Creator: Calkins, G. D. & Filbert, R. B., Jr.
Partner: UNT Libraries Government Documents Department
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Creep of 2S-O Aluminum Sheet at 500 and 550 C

Description: Abstract: "Creep and creep-rupture tests were made on 25-O aluminum sheet at temperatures of 500 and 550 C. The estimated stresses that will produce 0.5 per cent deformation and rupture in 10,000 hours at 400, 450, 500, and 550 C (data at 400 and 450 C are from BMI-T-29, dated June 9, 1950) are presented."
Date: September 11, 1952
Creator: VanEcho, J. A.; Simmons, W. F. & Cross, H. C.
Partner: UNT Libraries Government Documents Department
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Progress Report on Refining of MgX and Other Uranium-Bearing Materials

Description: From abstract: "Results of two methods of reducing the phosphate and vanadate contents of MgX, a uranium precipitate from the Belgian Congo, are described...Chemical analyses of several samples of pitchblende and MgX are presented."
Date: August 31, 1950
Creator: Ewing, R. A.; Kiehl, S. J., Jr. & Bearse, A. E.
Partner: UNT Libraries Government Documents Department
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Hydroxides as Moderator Coolants in Power-Breeder-Reactors

Description: The following report describes work that was udertaken to determine whether a homogeneous breeder reactor using an alkili metal hydroxide solution is capable of breeding.
Date: March 26, 1952
Creator: Dayton, Russell Wendt & Chastain, Joel W.
Partner: UNT Libraries Government Documents Department
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Uranium recovery from a low-grade Katanga sulfide concentrate : topical report

Description: A report which describes a variety of methods for processing a low-grade sulfide concentrate from the Congo. This concentrate consists primarily of sulfides of cobalt, nickel, and iron, plus about 10 percent uranium, present principally as uraninite.
Date: 1953
Creator: Bearse, A. E.; Ewing, R. A.; Sclar, C. B. & Pobereskin, M.
Partner: UNT Libraries Government Documents Department
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Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 1. Laboratory Investigations

Description: Report discussing laboratory investigations of thorium nitrate purification. Batch equilibrium data, solubility data, viscosity data, density data, and the results seven batch countercurrent extraction tests and two selective stripping tests are included.
Date: July 31, 1952
Creator: Ewing, R. A.; Fishel, J. B.; Kiehl, S. J., Jr.; Sharpe, R. E. & Bearse, A. E.
Partner: UNT Libraries Government Documents Department
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The Ammonium Carbonate Pressure Leaching of Uranium Ores Proposed as Feed to the Pilot Plant at Grand Junction, Colorado : Progress Report

Description: From introduction: This is Progress report BMI-282, the first of a series covering the operation of the pressure-leaching towers for the extraction of uranium by an ammonium carbonate leach...This report discusses the data obtained from tests run to show the effects of such variables as the amount of air and carbon dioxide passed through the pulp, temperature, pressure, and concentration of ammonium carbonate and ammonium bicarbonate in the leach solution on the extraction of uranium.
Date: June 15, 1955
Creator: Wheeler, C. M.; Langston, B. G. & Stephens, F. M., Jr.
Partner: UNT Libraries Government Documents Department
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A Study of Thorium-Base Alloys

Description: Report discussing studies testing various thorium alloys consisting of either Ames thorium and up to 5% of various additions or Ames thorium and up to 50% uranium. Effects of molybdenum additions for fusion welding, and cold-work strengthening were also tested. Methods, experimental data, and discussion is included.
Date: December 26, 1951
Creator: Goldhoff, R. M.; Ogden, Horace R. & Jaffee, Robert Isaac, 1917-
Partner: UNT Libraries Government Documents Department
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Topical report on examination of residues from the nitric acid digestion of pitchblende

Description: A report about an investigation started to determine the compounds and/or minerals present in the residue resulting from nitric acid digestion of ore. Emphasis was placed on determining the compounds and/or minerals containing boron.
Date: 1950
Creator: Langston, B.; Tangel, O. F. & Richardson, A. C.
Partner: UNT Libraries Government Documents Department
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Progress Report on Refining of MgX and Other Uranium-Bearing Materials

Description: Abstract: "The effects of acidity on extraction of vanadium and molybdenum by diethyl ether are described. Solubility data for several vanadium compounds in nitrate process solutions are presented. Preliminary results on the extraction of uranium from process slurries by tributyl phosphate are reported, including data on the contaminants extracted with the uranium."
Date: November 15, 1950
Creator: Ewing, R. A.; Belcher, R. L.; Kiehl, S. J., Jr. & Bearse, A. E.
Partner: UNT Libraries Government Documents Department
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Progress Report for the Month of January, 1952

Description: This progress report of the Battelle Memorial Institute covers information in many categories. These include development of ceramic fuel elements, general ceramics, uranium and its alloys, thorium and its alloys, development of metallic fuel elements and assemblies, metals and alloys for reactor components, miscellaneous metallurgical work, liquid coolants and fuels, reactor engineering studies, and mechanism development.
Date: February 1, 1952
Creator: Russell, H. W.; Nelson, H. R. & Dayton, R. W.
Partner: UNT Libraries Government Documents Department
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Progress Report on Refining of MgX and Other Uranium-Bearing Materials

Description: From abstract: "Results of tests investigating the effects of feed and scrub acidities on the extraction of uranium and contaminants from process slurries by tributyl phosphate-Gulfspray Naphtha in a Scheibel continuous extractor are described. Studies on the fractional precipitation of MgX from a dilute sulfuric acid system throw considerable light on the probable constitution of MgX. Further data on the effect of acidity on the extraction of molybdenum and vanadium into ethyl ether are presen… more
Date: November 30, 1950
Creator: Ewing, R. A.; Belcher, R. L.; Kiehl, S. J., Jr. & Bearse, A. E.
Partner: UNT Libraries Government Documents Department
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Tungsten-Arc Welding of Ames Thorium and Thorium Alloys

Description: This report follows an investigation made on the welding of Ames thorium by the inert-gas-shielded tungsten-arc process as the first part of a program on the joining of thorium. This program is part of a broader research program to develop the technology of thorium.
Date: January 15, 1952
Creator: Monroe, Robert E.; Martin, D. C. & Voldrich, C. B.
Partner: UNT Libraries Government Documents Department
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Progress Report on Refining of MgX and Other Uranium-Bearing Materials

Description: From abstract: "Results are presented which suggest the possibility of satisfactorily extracting uranium from pitchblende feeds with neutral ether, without the necessity of removing sulfate, by the addition of a sufficient quantity of iron to the feed." Other factors' effects on extraction were tested and arsenic was traced throughout extraction.
Date: September 30, 1951
Creator: Ewing, R. A.; Kiehl, S. J., Jr.; Bearse, A. E. & Sharpe, R. E.
Partner: UNT Libraries Government Documents Department
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Progress Report on the Concentration of Pitchblende

Description: Abstract: "The results of leaching studies on sulphide froth products obtained from the flotation of high-sulphur pitchblende are presented. The distribution of molybdenum in flotation products is also given. The flotation test at Middlesex is evaluated."
Date: December 31, 1950
Creator: Wesner, A. L.; Tangel, O. F. & Richardson, A. C.
Partner: UNT Libraries Government Documents Department
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Creep Strength of Uranium Alloys at 1500 and 1800 F

Description: Abstract:"The creep resistance of various uranium binary alloys was investigated at 1500 and 1800 F in vacuum. Tests were made on alloys of uranium with beryllium, columbium, molybdenum, tantalum, titanium, and zirconium and on molybdenum-UO2 composites. Of the alloys examined, those of the uranium-molybdenum system exhibited the best creep resistance. At 1500 F, creep rates of about 0.005%/hr were produced in uranium-molybdenum alloys by a stress of 2500 psi and, at 1800 F, similar creep rates… more
Date: May 28, 1953
Creator: Saller, Henry A.; Stacy, J. T.; Eddy, N. S. & Klebanow, H. L.
Partner: UNT Libraries Government Documents Department
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The Fabrication of Stainless Steel-Uranium Dioxide Fuel Elements

Description: Abstract: "Stainless steel-clad fuel sheet 0.020 in. thick with a 0.008-in. core of stainless steel plus UO2 was produced by roll cladding a powder metal compact. The effects of processing variables, core-matrix composition, quantity of oxide, and oxide particle size on the properties of the sheet were investigated. The strength and ductility of the core decreased sharply as the quantity of oxide in the core increased from 20 to 40 w/o. Over the range of matrix compositions investigated the par… more
Date: March 2, 1954
Creator: Keeler, J. R.; Keller, D. L. & Cuddy, L. J.
Partner: UNT Libraries Government Documents Department
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Corrosion of Type 347 Stainless Steel in the Uranium-Derby Pickle Bath

Description: Abstract: In one of the final stages of the process at the Mallinckrodt Uranium Refining Center, a 45 per cent nitric acid solution at about 170 F is used to pickle the calcined magnesium fluoride scale off the uranium derbies. The increase in the fluoride-ion content of the bath tends to promote corrosion of the Type 347 stainless tanks. This attack becomes excessive if 0.3 g/liter of fluoride ion or more is present. It was found that if aluminum ion is added to the solution the corrosiveness … more
Date: July 14, 1954
Creator: Peoples, R. S.; Fink, F. W.; Stewart, O. M. & Braun, W. J.
Partner: UNT Libraries Government Documents Department
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