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Electroplates on Thorium

Description: 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.
Partner: UNT Libraries Government Documents Department
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The Fabrication of Thorium Tubes

Description: 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.
Partner: UNT Libraries Government Documents Department
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Protective Coatings for Molybdenum

Description: 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.
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 Solubility of Oxygen in Uranyl Sulphate Solutions at Elevated Temperatures

Description: 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.
Partner: UNT Libraries Government Documents Department
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The Ductility of Brazed Stainless Steel Joints

Description: 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 1… more
Date: July 8, 1953
Creator: Saller, Henry A.; Stacy, J. T. & Eddy, N. S.
Partner: UNT Libraries Government Documents Department
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The Application of Ceramics to Hanford Fuel Elements

Description: 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.
Partner: UNT Libraries Government Documents Department
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Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

Description: 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… more
Date: January 15, 1953
Creator: Ewing, R. A.; Pobereskin, M.; Kiehl, S. J.; Foley, D. D.; Filbert, Robert B.; Kimball, R. B. et al.
Partner: UNT Libraries Government Documents Department
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Determination of Rare Earths in Refined Uranium : Topical Report

Description: 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… more
Date: June 30, 1953
Creator: Ewing, R. A. & Bearse, A. E.
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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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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Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

Description: 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.
Partner: UNT Libraries Government Documents Department
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Corrosion of Uranium Alloys in High-Temperature Water

Description: 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-
Partner: UNT Libraries Government Documents Department
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Welded Closures for Fuel Elements

Description: 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.
Partner: UNT Libraries Government Documents Department
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Bonding of uranium and zirconium alloys

Description: 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.
Partner: UNT Libraries Government Documents Department
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Preparation and Properties of the Eutectic Uranium-Chromium Alloy

Description: 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.
Partner: UNT Libraries Government Documents Department
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Uranium Migration in UO₂-Bearing Ceramics

Description: 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.
Partner: UNT Libraries Government Documents Department
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Differential Thermal-Expansion Effects on Brazed Joints

Description: 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 al… more
Date: September 4, 1953
Creator: Saller, Henry A.; Baroody, Eugene Michael, 1914-1982; Deem, H. W.; Stacy, J. T. & Klebanow, H. L.
Partner: UNT Libraries Government Documents Department
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Fused Salt Mixtures as Potential Liquid Fuels for Nuclear Power Reactors

Description: 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.
Partner: UNT Libraries Government Documents Department
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Investigation of the Behavior of NaOH-UO₃ Slurries in Small Flow Loops

Description: From introduction: "This report presents the results of an experimental program to evaluate engineering problems which might be encountered when circulating NaOH-UO3 slurry through a thermal cycle."
Date: September 15, 1953
Creator: Stang, J. H.; Lagedrost, J. F.; Simons, E. M. & Dayton, R. W.
Partner: UNT Libraries Government Documents Department
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Ternaries of the eutectic uranium-chromium alloy

Description: A report about a study about the effect of small additions of iron, nickel, and manganese to the uranium - 5 wt % chromium eutectic alloy.
Date: 1953
Creator: Saller, Henry A.; Rough, Frank A. & Bauer, A. A.
Partner: UNT Libraries Government Documents Department
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Temperature distributions in a reactor fuel plate

Description: Report detailing local heat-transfer coefficients as they relate to temperature distribution in reactor fuel plates.
Date: 1953
Creator: Chastain, Joel W.; Long, J. K.; Redmond, R. F.; Grimble, R. E. & Dayton, R. W.
Partner: UNT Libraries Government Documents Department
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