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Electroplates on Thorium (open access)

Electroplates on Thorium

Abstract: "The protection of thorium in hot water was studied. Copper electrocladding on thorium offers promising protection against hot water. The corrosion of thorium in 95 C water was reduced appreciably by a thorium phosphate film. The results of this abbreviated investigation offer a basis for the development of a method of protecting thorium at elevated temperatures in corrosive media."
Date: January 9, 1953
Creator: Beach, John G.; Schickner, W. C.; Vaaler, L. E. & Faust, Charles L.
System: The UNT Digital Library
The Fabrication of Thorium Tubes (open access)

The Fabrication of Thorium Tubes

Abstract: "Thorium tubes were cold drawn from extruded tube stock and also from drilled hot-rolled rod. Total reductions up to approximately 85 per cent were accomplished by conventional tube-drawing methods, without an intermediate anneal. The hard-drawn tubes had high tensile strength, but the ductility, as indicated by flaring and flattening tests, was low."
Date: January 16, 1953
Creator: Saller, Henry A. & Keeler, J. R.
System: The UNT Digital Library
Protective Coatings for Molybdenum (open access)

Protective Coatings for Molybdenum

Report discussing studies on various types of protective coatings for a molybdenum sheet. Procedures, materials, and results of each coating are included.
Date: February 17, 1953
Creator: Powell, Carroll F.; Jones, R. P.; Secrest, A. C.; Sherwood, E. M. & Campbell, Ivor E.
System: The UNT Digital Library
Creep Strength of Uranium Alloys at 1500 and 1800 F (open access)

Creep Strength of Uranium Alloys at 1500 and 1800 F

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 were obtained in composites of 90 wt % molybdenum-10 wt % UO2 by a stress of 12,000 psi."
Date: May 28, 1953
Creator: Saller, Henry A.; Stacy, J. T.; Eddy, N. S. & Klebanow, H. L.
System: The UNT Digital Library
The Solubility of Oxygen in Uranyl Sulphate Solutions at Elevated Temperatures (open access)

The Solubility of Oxygen in Uranyl Sulphate Solutions at Elevated Temperatures

Abstract: "The solubility of oxygen in uranyl sulphate solutions and in water at 212, 275, and 325 F, and at oxygen partial pressures up to 1500 psia was investigated. The results are presented in tabular and graphic form. The solubility is proportional to the partial pressure of oxygen. The ratio of solubility in the uranyl sulphate solution to solubility in water at the same temperature and pressure is a function of the concentration of the salt in solution."
Date: June 10, 1953
Creator: Pray, H. A. & Stephan, Elmer F.
System: The UNT Digital Library
The Ductility of Brazed Stainless Steel Joints (open access)

The Ductility of Brazed Stainless Steel Joints

Abstract: "The ductility of Type 310 stainless steel T-joints brazed with GE-62 brazing alloy was measured at room temperatures 1200, 1650, and 1800 F. The measure of ductility was taken as the plastic axial strain required to crack braze fillets in T-section tensile specimens. At elevated temperatures, the ductility of as-brazed joints approximated that of the stainless steel, but at room temperature the brazed joints had only one-tenth the ductility of the base metal. Annealing for 16 hr at 1800 F in air was found to triple the room-temperature ductility of the brazed joint."
Date: July 8, 1953
Creator: Saller, Henry A.; Stacy, J. T. & Eddy, N. S.
System: The UNT Digital Library
The Application of Ceramics to Hanford Fuel Elements (open access)

The Application of Ceramics to Hanford Fuel Elements

From introduction: This work is a survey of possible uses of ceramic materials in Hanford-type fuel elements.
Date: September 4, 1953
Creator: King, B. W.; Tripp, H. P. & Duckworth, W. H.
System: The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

Abstract: "Dissolution of carnotite in several readily liquefiable gases, including ammonia, sulfur dioxide, chlorine, and nitrogen dioxide, was found to be negligible, even in the presence of uranium complexing agents. No low-boiling liquids have been found which will dissolve carnotite directly. Treatment with various sulfur chloride will convert carnotite to a form soluble in water or in certain organic solvents. Also, carnotite can be readily dissolved in HCl-acidified ethanol, methanol, or acetone. Amenability tests on nine western ores with HCl-methanol solvent indicated that uranium extractions greater than 90 per cent could be obtained if sufficient acid was used to insure some free acidity in the pregnant liquor. Temple Mountain and Sinbad-Muddy River ores were exceptions to this, uranium extractions being only about 50-60 per cent. Vanadium extractions were invariably lower than uranium extractions. Chemical analyses are presented for nine western ores."
Date: January 15, 1953
Creator: Ewing, R. A.; Pobereskin, M.; Kiehl, S. J.; Foley, D. D.; Filbert, Robert B.; Kimball, R. B. et al.
System: The UNT Digital Library
Determination of Rare Earths in Refined Uranium : Topical Report (open access)

Determination of Rare Earths in Refined Uranium : Topical Report

Abstract: "Rare-earth analyses were performed on several samples of refined uranium oxide and nitrate, using a modified cellulose column procedure. Rare earths were not detectable in samples of 0.03 shotgun of less. Detection limits were from 0.0005 to 0.015 ppm. Negligible quantities of low-cross-section rare earths were found in less pure uranium samples, obtained during start-up operations of the pilot plant at the Feed Materials Production Center, primarily those rare earths of greater than average abundance in nature. No correlation was found between rare-earth content and shotgun values. Rare earths do not appear to be contributing significantly to the neutron absorption of refined uranium. A modified cellulose column procedure, which includes a preconcentration solvent-extraction step, is described. Radioactive tracer tests indicating rare-earth recoveries by the method of >98 per cent are reported."
Date: June 30, 1953
Creator: Ewing, R. A. & Bearse, A. E.
System: The UNT Digital Library
Identification of Reaction Products Formed During Magnesium Reduction of Uranium Tetrafluoride: Report (open access)

Identification of Reaction Products Formed During Magnesium Reduction of Uranium Tetrafluoride: Report

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.
System: The UNT Digital Library
Corrosion-Resistant Materials for Hydrofluoric Acid : Progress Report (open access)

Corrosion-Resistant Materials for Hydrofluoric Acid : Progress Report

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.
System: The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

This report describes progress in testing non-aqueous extraction methods for leaching Western ores of uranium and vanadium.
Date: April 15, 1953
Creator: Ewing, R. A.; Pobereskin, M.; Kimball, R. B. & Bearse, A. E.
System: The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

The following progress report is part of a series of reports on the study of nonaqueous extractive methods for western uranium ores. This report continues studies on HCl-methanol leaching of Western ores, primarily on Temple Mountain ores.
Date: July 15, 1953
Creator: Ewing, R. A.; Pobereskin, M.; Kiehl, S. J.; Foley, D. D.; Filbert, Robert B.; Kimball, R. B. et al.
System: The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

This report describes progress in testing nonaqueous extractive methods for leaching Western ores of uranium and vanadium
Date: October 20, 1953
Creator: Ewing, R. A.; Pobereskin, M.; Kimball, R. B. & Bearse, A. E.
System: The UNT Digital Library
Notes on Evaporation of Target Materials (open access)

Notes on Evaporation of Target Materials

Abstract: "The general utility of vacuum evaporated films is discussed. The characteristics that makes this technique most useful are the uniformity of the films, the easy control of their thickness over a large range, and the adaptability of the system to different metals and compounds. The design of a vacuum evaporator should provide adequate pumping speed, cooling of components, filament heater supply, and general flexibility and adaptability of the components to different materials. The design of filaments or boats and the evaporation of Al, Ag, Au, Li, Na, UCl4, ThF4, Be, SiO, Nal (Tl), U, and UO2 are considered. Special attention is given to the problem of obtaining uniform layers of UO2 on a large, flat target relatively close to the source."
Date: March 1953
Creator: Northrop, J. A. & Stokes, R. H.
System: The UNT Digital Library
Los Alamos Power Reactor Experiment and its Associated Hazards (open access)

Los Alamos Power Reactor Experiment and its Associated Hazards

The following report describes the high pressure and temperature homogeneous reactor experiment which has been started at Los Alamos, as well as the hazards and safety aspects for the experiments.
Date: December 2, 1953
Creator: King, L. D. P.
System: The UNT Digital Library
Corrosion of Uranium Alloys in High-Temperature Water (open access)

Corrosion of Uranium Alloys in High-Temperature Water

This report is one of a series of five, dealing with alloys of the uranium-zirconium series. Particularly, this report focuses on the corrosion properties of uranium alloys, with zirconium as the major alloying agent, in high-temperature water.
Date: 1953
Creator: Pray, H. A. & Berry, Warren E., 1922-
System: The UNT Digital Library
Welded Closures for Fuel Elements (open access)

Welded Closures for Fuel Elements

From abstract: "The inert-gas metal-arc welding process was used to determine weldability studies of various aluminum alloys that are being considered for use as can materials. The solid-phase and induction welding processes were also investigated for making can closures."
Date: October 8, 1953
Creator: Sopher, R. P.; Martin, G. E.; Grable, G. B.; Voldrich, C. B.; Leatherman, A. F. & Todd, F. C.
System: The UNT Digital Library
Bonding of uranium and zirconium alloys (open access)

Bonding of uranium and zirconium alloys

Report describing a study of fabricating conditions for bonding zirconium and uranium alloys by roll cladding.
Date: 1953
Creator: McIntire, H. O.; Hucek, H. J. & Manning, G. K.
System: The UNT Digital Library
Preparation and Properties of the Eutectic Uranium-Chromium Alloy (open access)

Preparation and Properties of the Eutectic Uranium-Chromium Alloy

This report follows the study of the properties of eutectic uranium-chromium alloy which is of interest in the Dow-Detroit Edison power reactor. The reactor is described in this report, as well as the casting of alloy, shrinkage measurements during solidification, density measurements, microstructures and macrostructures, mechanical properties, and specific heat data.
Date: November 3, 1953
Creator: Saller, Henry A.; Rough, Frank A. & Dickerson, Ronald F.
System: The UNT Digital Library
Survey of Materials for Supercritical-Water Reactor (open access)

Survey of Materials for Supercritical-Water Reactor

Survey of properties of materials which might be suitable for use in various locations in a supercritical-water reactor. Properties examined include tensile strength, rupture strength, endurance strength, Young's modulus, tensile elongation, coefficient of thermal expansion, coefficient of thermal conductivity, density, nominal composition, usual heat treatments and thermal-neutron-absorption cross sections.
Date: November 27, 1953
Creator: Udy, Murray C. & Boulger, Francis W.
System: The UNT Digital Library
Uranium Migration in UO₂-Bearing Ceramics (open access)

Uranium Migration in UO₂-Bearing Ceramics

This report follows a preliminary study on uranium migration in pressed and sintered UO2-bearing bodies based on MoSi2 or Al2O3.
Date: September 4, 1953
Creator: Quirk, J. F.; Smalley, A. K.; Duckworth, W. H. & Ferrell, Edward Francis.
System: The UNT Digital Library
Differential Thermal-Expansion Effects on Brazed Joints (open access)

Differential Thermal-Expansion Effects on Brazed Joints

Abstract: "Differential thermal-expansion effects in brazed joints involving Type 310 stainless steel and GE-62 brazing alloy were investigated. The work included dilation and modulus-of-elasticity measurements using homogenous cast specimens and observations on bimetallic cantilevers made of the two constituents. No anomalies were found, although there were irregularities in the expansion of the brazing alloy which were ascribed to a solubility phenomenon. The elastic modulus of the brazing alloy was determined. Cantilever deflections with temperature and with load were measured, and the results were interpreted using equations which treat the specimens as true bimetals consisting of two homogeneous components. The difference in thermal-expansion coefficients obtained in this way from the temperature-deflection data was consistent with the dilation measurements. The load measurements yielded an average elastic modulus for the bimetal which was about two-thirds of what would have been expected from knowledge of the components. This discrepancy probably arose from porosity which was observed in the braze components."
Date: September 4, 1953
Creator: Saller, Henry A.; Baroody, Eugene Michael, 1914-1982; Deem, H. W.; Stacy, J. T. & Klebanow, H. L.
System: The UNT Digital Library
Fused Salt Mixtures as Potential Liquid Fuels for Nuclear Power Reactors (open access)

Fused Salt Mixtures as Potential Liquid Fuels for Nuclear Power Reactors

From introduction: "This report summarizes the work done on a study of fused-salt systems in a search for new liquid fuels suitable for use in a nuclear power reactor."
Date: September 8, 1953
Creator: Crooks, R. C.; Snyder, M. J. & Clegg, J. W.
System: The UNT Digital Library