UNT Libraries Government Documents Department - 125 Matching Results

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Freezing Point Diagram and Liquid-Liquid Solubilities of the System Uranium Hexafluoride-Hydrogen Fluoride

Description: Abstract: "The complete freezing point diagram for the system uranium hexafluoride-hydrogen fluoride has been determined. In addition, liquid-liquid solubilities of these compounds have been measured up to the consolute temperature of 101 C. A miscibility gap starts at 61.2 C. over the compositions range 10 to 80 mole per cent uranium hexafluoride. The lowest melting point of this binary system under its own pressure, i.e. the eutectic, is -85 C."
Date: December 28, 1952
Creator: Rutledge, Gene P.; Jarry, Roger L. & Davis, W., Jr.

Mechanical Properties of Zirconium-Tin Alloys

Description: Abstract: "The mechanical properties and corrosion resistance of induction-melted, zirconium-tin alloys have been determined. The alloys investigated contained from zero to five per cent tin and up to 0.3% carbon. The zirconium used was United States Bureau of Mines sponge zirconium. The mechanical properties investigated include the tensile, hot-hardness, and impact properties."
Date: December 22, 1952
Creator: Schwope, A. D. & Chubb, Walston

Heavy Aggregate Investigation

Description: This report follows a manuscript report made in January 11, 1952, and provides results of a survey that gives corrections as well as suggestions for new and local sources of aggregate material in comparison to the original report. These reports were made in response to a heavy desire of improvement in reactor design and shielding.
Date: December 19, 1952
Creator: Brown, R. E.

X-ray Photometric Assay of Plutonium in Metal Castings

Description: This following report discusses certain topics pertinent to the x-ray photometric method, such as the optimum size of sample and of sample concentration, the technique of measurement for high precision, the use of easily prepared uranium standards for future calibrations and corrections for extraneous substances, and it compares results obtained by both x-ray and chemical assays.
Date: December 12, 1952
Creator: Lambert, M. C.

Nitration Reactions of Shell Spray Base under Purex Waste Recovery Process Conditions

Description: Abstract: "Experiments were performed to characterize the types of nitro compounds that might be formed by reaction of Shell Spray Base with nitric acid, to determine the extent of their formation, if any, and their path under conditions of nitric acid recovery in the Purex Process. It is concluded that the instability of Shell Spray Base to nitration, under conditions to prevail in the plant, presents neither a disposal problem nor a safety problem."
Date: December 5, 1952
Creator: Wagner, R. M.

Dissolution of NaK

Description: Abstract: "A rapid yet safe method for the dissolution of sodium-potassium alloys prior to chemical or instrumental analysis has been devised. The alloy is submerged beneath the surface of an inert organic reagent and dissolved at a controlled rate by adding methanol drop-by-drop. A blanket of inert gas is maintained over the reaction flask. The procedure has been successfully used to dissolve samples of NaK in the range of 0.05 to 25 grams."
Date: December 2, 1952
Creator: White, J. C.; Talbott, C. K. & Brady, L. J.

Initial Investigation of the Mechanical Properties of Uranium at Elevated Temperatures

Description: Introduction: "Knowledge of the mechanical properties of uranium at elevated temperature is essential in order to understand and predict the fabrication characteristics and pile behavior of this metal. This report presents the experimental data obtained from beta heat-treated specimens which were originally machined from one production, alpha-rolled uranium rod."
Date: December 2, 1952
Creator: Hueschen, R. E. & Pitt, C. H.

Evaluation of Oxidation-Resistant Ceramics for High-Temperature Reactor Elements

Description: Abstract: "As a possible aid in the selection of ceramic materials for use in the fabrication of high-temperature reactor elements, the reported properties of 23 refractory oxidation-resistance ceramic compounds are tabulated. The thermal stresses and heat throughout capacities for nine of these compounds are estimated for conditions of steady heat flow and uniform heat generation in the temperature range of 1500 to 2500 F. The compounds studied have macroscopic thermal-neutron-absorption cross sections lower than 0.2 per centimeter. Data concerning the high-temperature stability of uranium compounds are tabulated for those with melting points above 2450 F."
Date: December 1, 1952
Creator: Harman, Cameron G.; Ferrell, Edward Francis.; Wagner, H. E. & Quirk, J. F.

Neoprene and Nickel Linings : NYX Test No. 1.3.4

Description: Abstract: "Stainless steel valves, pumps, and heat exchangers were not available for NYX start-up. Cast iron and steel equipment was protected against corrosion by lining with neoprone and nickel plate. The linings failed under flow conditions and their use was discontinued. Chromate inhibitor was used to reduce rusting for the reminder of the test program."
Date: December 1952
Creator: Poss, Fred J. & Longtin, Bruce

Corrosion Tests : SAE 1010 Mild Steel in Synthetic Neutralized Redox Waste Solution

Description: From introduction: "This report gives the results of a 1000-hour corrosion test of SAE 1010, low carbon steel, in synthetic Redox waste solutions...The present test was designed to obtain corrosion rates for waste solution temperatures of 180 F, 200 F, and 220 F in solutions neutralized to pH values of 11, 12, and 13.
Date: November 13, 1952
Creator: Endow, Noborn

Heat and Free Energy of the Reaction AmCl₃s + H₂O(g) = AmOCl(s) + 2HCl(g)

Description: In a previous paper a method of measuring the equilibrium constants at various temperatures for the titular reaction has been described. This report applies the method to an investigation of the corresponding reaction of americium, representing a part of a systematic program of investigation of the thermodynamic properties of analogous reactions of lanthanide and actinide elements.
Date: November 10, 1952
Creator: Koch, C. W. & Cunningham, Burris Bell, {}

The Uranium-Titanium Alloy System

Description: Abstract: "A uranium-titanium constitution diagram is presented. There is complete solid solubility between titanium and gamma uranium above about 2100 F. Only one compound exists in the system. It has a hexagonal structure based on U2Ti. It has a fairly wide range of stability, particularly on the titanium side. Beta-titanium solid solution decomposes eutectoidally into alpha titanium and compound at 1150 F. Eutectoid composition is about 72 atomic per cent titanium. Gamma-uranium solid solution decomposes eutectoidally at 1325 F into beta uranium and compound. Eutectoid composition is about 6 atomic per cent titanium. Beta uranium and compound react peritectoidally at 1233 F to give alpha uranium. Solubility of titanium in alpha and beta uranium is low as is the solubility or uranium in alpha titanium."
Date: November 5, 1952
Creator: Udy, Murray C. & Boulger, Francis W.

Evaluation of Type 304 Stainless Steel as a Substitute for Type 347

Description: Abstract: "Type 347 stainless steel was selected for SIR applications requiring resistance to corrosion in sodium on the basis of limited corrosion data and extrapolation of experience in aqueous media. Subsequent testing indicated that carbide stabilization was not necessary for good resistance to corrosion in sodium. Evaluation of the unstabilized grade of 18-8 stainless steel, Type 304, was intensified because it offered a number advantages over Type 347. Type 304 was more readily available, required fewer strategic materials, was less expensive, and was reported to be weldable with less difficulty. From the results of this investigation, it appears that Type 304 can be substituted for 347 for all SIR applications where the slightly higher elevated temperature strength of 347 is not required."
Date: November 3, 1952
Creator: Koenig, R. F.

Mechanical Properties of Iodide Zirconium Alloys

Description: Introduction: "The tensile properties, hot hardness, impact strength; and corrosion resistance of some arc-melted, iodide zirconium alloys have been determined. The alloys investigated include binary alloys of zirconium containing zero to five per cent tin, binary alloys of zirconium containing zero to 0.14 per cent nitrogen, and ternary alloys of zirconium containing tin and nitrogen, tin and uranium, and uranium and beryllium."
Date: November 1, 1952
Creator: Schwope, A. D. & Chubb, Walston

Development of the Hanford Slave Manipulator for Use in the Multicurie Cells at Hanford

Description: Introduction: "During the early planning of the multicurie cells at Hanford it was decided that a slave type manipulator would be necessary to perform the experiments for which the cells were being designed. The design required steel roofs for installation through a port hole in the face. Technical Services Equipment Development began developing the proposed manipulator in January 1951 by making a study of those existing at that tune. None met the requirements which had been established; therefore, the design of a special manipulator was started immediately."
Date: October 31, 1952
Creator: Field, Richard E. & Gifford, John F.

Determination of Americium

Description: The following report describes a successful procedure used for the determination of americium in the presence of plutonium. Provided are articles listed that describe the research done in developing the method.
Date: October 15, 1952
Creator: Schmidt, H. R.

Improved Spectrographic Analysis of Uranium and Plutonium by the Carrier Concentration Method

Description: Introduction: "The carrier (pyroelectric) concentration method is commonly used in the spectrographic analysis of plutonium metal. This report describes work which lead to substantial improvements in accuracy, precision and ease with which the analysis is made. Included are data from analyses of plutonium metal by the original and the improved carrier methods, and the cupferron extraction method."
Date: October 7, 1952
Creator: Daniel, J. L.