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Fast-Neutron and Gamma Spectrum and Dose in Beryllium Oxide

Description: This report follows a series of tests run to determine the shielding properties of beryllium oxide, conducted at the Battelle Lid-Tank Shielding Facility. Neutron and gamma penetrations through and behind beryllium oxide were measured.
Date: January 11, 1961
Creator: Klingensmith, Raymond W.; Jung, Richard G.; Lindgren, William A.; Epstein, Harold M. & Chastain, Joel W., Jr.
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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.
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Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 2. Mixer-Settler Pilot Plant Investigations

Description: From abstract: "This report describes the construction and operation of a mixer-settler pilot plant for the purification of mantle-grade thorium nitrate. The liquid-liquid extraction process utilized 30% tributyl phosphate - 70% 'Solvesso-100' as the organic solvent and nitric acid as the salting agent. Continuous steady-state operation of the equipment was demonstrated, with very good recovery of thorium."
Date: July 31, 1952
Creator: Burkhart, C. A.; Foley, D. D.; Retzke, F. A.; Filbert, Robert B., Jr. & Clegg, John W.
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Final Report on Recovery of Thorium and Uranium From Monazite Sand : Volume 1

Description: Report describing a method for recovery of high yields of thorium and uranium from monazite sand concentrates. Monazite is decomposed into hydrous metal oxides, which are dissolved in an acid. The solution is then separated into a precipitate, which seperates from thorium and uranium. An alternate separation method is evaluated.
Date: September 15, 1950
Creator: Calkins, G. D.; Filbert, R. B., Jr.; Bearse, A. E. & Clegg, J. W.
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Further Studies with the GCRE Critical-Assembly

Description: This report follows ciritical-assembly studies on: the effect on reactivity caused by changes in axial reflector materials; the effect on reactivity and the power perturbation caused by fast safety control-blade guides; the effect of changes in fuel-element material composition; the effect of changes in fuel-elements spacing designed to produce uniform radial power-generation rates.
Date: December 29, 1958
Creator: Dingee, David A.; Ballowe, William C.; Egen, R. A.; Jankowski, Francis J. & Chastain, Joel W.
open access

GCRE Critical-Assembly Studies

Description: This report follows critical-assembly studies made to provide engineering and physics data to aid in developing the Gas Cooled Reactor Experiments.
Date: September 10, 1958
Creator: Dingee, David A.; Ballowe, William C.; Klingensmith, Raymond W.; Egen, R. A.; Jankowski, Francis J. & Chastain, Joel W.
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Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Heat Treatment

Description: Introduction: "The uranium-5 w/o chromium alloy has been intensively investigated for use in a power reactor in the as-cast condition. However, when cast sample fuel elements were subjected to irradiation, their stability was found to be unsatisfactory. In order to improve the behavior of the alloy, a program of grain refinement by heat treatment was begun. The effect of chill casting on the heat-treated grain size was also investigated."
Date: May 13, 1955
Creator: Saller, Henry A.; Rough, Frank A. & Bauer, Arthur A.
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Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Ternary Additions

Description: Abstract: "Refinement of grain size of the base uranium-chromium eutectic alloy (uranium-5 w/o chromium) by ternary additions is discussed. Thirteen additions to the base alloy were investigated, and three additions were found to exhibit worthwhile grain-refinement tendencies. The three alloys, uranium-5 w/o chromium-0.2 w.o molybdenum, uranium-5 w/o chromium-0.2 w/o germanium, and uranium-5 w/o chromium-0.2 w/o niobium, were heat treated to produce final grain-size structures of between 0.015 … more
Date: July 5, 1955
Creator: Saller, Henry A.; Dickerson, Ronald F.; Murr, William E. & Bauer, Arthur A.
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Grain Refinement of Uranium by Alloying

Description: Binary alloys of uranium with 38 elements in the range 0.01 to 1.0 at.% were made. Three alloys having nominal compositions of 0.01, 0.1, and 1.0 at.% were made with most of the elements, and in addition, 12 ternary and quaternary alloys were made. The alloys were cast, rolled to 7/8-inch-diameter bars, heat treated, and examined for grain size.
Date: June 1, 1951
Creator: Saller, Henry A.; Keeler, J. R. & Eddy, N. S.
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High-Boron Steels for Reactor Shielding

Description: This report follows work performed to determine the effects of large boron additions on the fabricability and room-temperature tensile properties of various steels for reactor shielding.
Date: September 27, 1955
Creator: Saller, Henry A.; Stacy, John T. & Klebanow, Herbert L.
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High-Temperature Oxidation Resistance of Thin Iron-Chromium-Aluminum Alloy Sheet

Description: Abstract: "The oxidation resistance of thin sheets of iron-28 w/o chromium-2.67 to 10.0 w/o alloys, nominally 0.004, 0.006, 0.008, 0.012, and 0.016 in. thick, was determined by exposure in static air for 100 hr at 2100 and 2300 F. A minimum of 3.67 and 9.37 w/o aluminum was necessary to prevent excessive oxidation of 0.004-in.-thick sheet material at 2100 and 2300 F, respectively. Correspondingly, specimens of lower aluminum content and greater thickness withstood the oxidation attack. Oxidatio… more
Date: October 22, 1957
Creator: Jablonowski, Edward J.; Shober, Frederic R. & Dickerson, Ronald F.
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Hydrogen Embrittlement of Zirconium

Description: Abstract: "The amount of hydrogen normally present in zirconium and zirconium alloys suffices to reduce their ductility greatly in an impact test at room temperature, after slow cooling from 600 F. Quenching from 600 F or above gives high impact strength, as does removal of hydrogen by high-temperature vacuum annealing. This report discusses the evidence on hydrogen embrittlement, the diffusion, solid solubility, and equilibrium pressure of hydrogen of hydrogen in zirconium, the microstructure,… more
Date: August 22, 1952
Creator: Dayton, Russell Wendt; Schwope, A. D.; Muehlenkamp, G. T.; Saller, Henry A.; Dickerson, R. F.; Schwartz, C. M. et al.
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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.
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Identification of Slag Constituents from Uranium Metal Production Bombs

Description: Abstract: "X-ray and microscopic examination of slags from uranium metal production bombs which gave good and bad yields in the plant at St. Louis have indicated the significance of uranium oxide formation. Apparently the oxide (UO2) results from reaction of the UF4 with linear material, particularly with moisture in the liner."
Date: January 31, 1952
Creator: Vaughan, D. A.; Cocks, G. G. & Schwartz, C. M.
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