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300-KV Pulser Transformer and Pulser. (open access)

300-KV Pulser Transformer and Pulser.

Photographs and working drawings are presented for a small (approximately 4.25 X 7 X 9 inch) 300Kv pulse transformer having double-conical secondaries each with a corona ring at its greatest diameter. The pulser circuit is shown but no text is included.
Date: November 1951
Creator: Heller, R. E.
Object Type: Report
System: The UNT Digital Library
The Action of Oxygen on Activated Charcoal (open access)

The Action of Oxygen on Activated Charcoal

The following report provides information conducted with the purpose of ascertaining the effect of oxygen on activated charcoal at approximately one atmosphere by measuring the amount of CO2 formed over a known length of time.
Date: June 29, 1951
Creator: Bigelow, J. E.; Belaga, M. W. & Mulvihill, R. J.
Object Type: Report
System: The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1950 (open access)

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1950

Technical report detailing expansion of the Aircraft Nuclear Propulsion at the Oak Ridge National Laboratory. Major facilities completed at this time were the Shielding Rector, the ANP Critical Facility, and the 86-in. Cyclotron. Outlines further need for radiation damage studies. [From Summary]
Date: February 27, 1951
Creator: Briant, R. C.; Ellis, C. B. & Cottrell, W. B.
Object Type: Report
System: The UNT Digital Library
Ames Laboratory Quarterly Summary Research Report: July-September 1951 (open access)

Ames Laboratory Quarterly Summary Research Report: July-September 1951

A report about metallurgy, chemistry, and physics of metals and alloys. Particular metals include zirconium, thorium, and vanadium metal as well as other earth metals.
Date: November 15, 1951
Creator: Dreeszen, W. E.
Object Type: Report
System: The UNT Digital Library
Ames Laboratory Quarterly Summary Research Report: Octoer - December 1950 (open access)

Ames Laboratory Quarterly Summary Research Report: Octoer - December 1950

A report about investigations of several binary alloy systems of thorium. Some of these alloys containing lead, molybdenum and tin have been prepared in the tungsten arc furnace.
Date: January 30, 1951
Creator: Dreeszen, W. E.
Object Type: Report
System: The UNT Digital Library
Analysis of Lid Tank Neutron Data for Lead and Iron (open access)

Analysis of Lid Tank Neutron Data for Lead and Iron

Abstract: An analysis of the lid tank neutron data for Pb-H2O and Fe-H2O is made. "Effective" fast neutron cross sections for the metals are obtained. This is based on the "one collision theory" of shielding. Values are 3.4 barns for Pb and 2.0 barns for Fe. These compare very well with those obtained by Albert and Welton based on other lid tank data and another method of calculation.
Date: January 5, 1951
Creator: Podgor, S.
Object Type: Report
System: The UNT Digital Library
Analytical Chemistry Division Quarterly Progress Report for Period Ending March 26, 1951 (open access)

Analytical Chemistry Division Quarterly Progress Report for Period Ending March 26, 1951

Technical report covering experiments happening on the Analytical Chemistry Division's sites at the Oak Ridge National Laboratory. Includes information on ionic analyses, radio-chemical analyses, spectrochemical analyses, service analyses, inorganic preparations, analytical chemical control of homogeneous reactor solution, optical and electron microscopy, and service analyses for the period ending March 26, 1951. [From Abstract]
Date: October 8, 1951
Creator: Kelley, M. T. & Susano, C. D.
Object Type: Report
System: The UNT Digital Library
Analytical Chemistry Division Quarterly Progress Report for Period Ending January 10, 1951 (open access)

Analytical Chemistry Division Quarterly Progress Report for Period Ending January 10, 1951

Technical report covering experiments happening on the Analytical Chemistry Division's sites at the Oak Ridge National Laboratory. Includes information on ionic analyses, radiochemical analyses, spectrochemical analyses, service analyses, inorganic preparations, analytical chemical control of homogeneous reactor solution, optical and electron microscopy, and service analyses. [From Abstract]
Date: March 28, 1951
Creator: Kelley, M. T. & Susano, C. D.
Object Type: Report
System: The UNT Digital Library
Analytical procedures for the metal fabrication process (open access)

Analytical procedures for the metal fabrication process

From introduction: The present report describes further refinements of the apparatus and the method to meet a need for a sensitive determination of carbon in plutonium.
Date: February 20, 1951
Creator: Leboeuf, M. B.
Object Type: Report
System: The UNT Digital Library
Analytical procedures for the plutonium Metal Fabrication Process (open access)

Analytical procedures for the plutonium Metal Fabrication Process

A report describing a the results of a fluorimetric and volumetric method for the determination of fluoride. This method was developed for the determination of ionizable fluorine in gases in the range of 1-500ppm. This method was chosen because the determination depends on the generation of a color rather than the bleaching effect or on a change of color.
Date: January 15, 1951
Creator: Kendall, L. F.
Object Type: Report
System: The UNT Digital Library
Analytical studies of the estimation of beryllium oxide in beryllium metal (open access)

Analytical studies of the estimation of beryllium oxide in beryllium metal

From abstract: The estimation of beryllium oxide in beryllium metal depending on the differential solubilities of the two material in dilute hydrochloric acid is presented. The results compare favorably with the present beryllium chloride volatilization procedure. Alternate methods are described, and the limitations and possible errors are discussed.
Date: April 17, 1951
Creator: Rynasiewicz, Joseph
Object Type: Report
System: The UNT Digital Library
Angular distribution of neutrons from a plane surface (open access)

Angular distribution of neutrons from a plane surface

From introduction: "This report determines lattice losses by considering the angular distribution of the neutrons emitted from the interior faces of the lattice and the exterior faces of the target. The purpose of this report is to investigate this problem by considering the dimensions of the faces to be large compared to the total mean free path."
Date: 1951
Creator: Harker, Wesley H.
Object Type: Report
System: The UNT Digital Library
Application of Heavy Media Separation, Flotation and Carbonate Leaching to Congo Ores (open access)

Application of Heavy Media Separation, Flotation and Carbonate Leaching to Congo Ores

The investigation of magnesitic-dolomite uranium ores from Union Miniere du Haute Katanga, Belgian Congo, was undertaken in order to examine the possibility of separating the uranium minerals from the carbonate minerals by Heavy Media Separation or froth flotation; thus reducing the sulfuric acid consumption during the uranium leach. In addition, the effect of carbonate leaching the whole ore and carbonate flotation products was examined.
Date: October 31, 1951
Creator: Breymann, John B.
Object Type: Report
System: The UNT Digital Library
The Application of Nuclear Track Emulsions to the Analysis of Urine for very Low Level Plutonium (open access)

The Application of Nuclear Track Emulsions to the Analysis of Urine for very Low Level Plutonium

The following document analyzes plutonium in urine which uses nuclear track film for evaluation of the quantity of separated plutonium.
Date: November 15, 1951
Creator: Schwendiman, L. C.; Healy, John W. & Reid, D. L.
Object Type: Report
System: The UNT Digital Library
The Argonne Heavy Water Reactor (CP-3 Prime) (open access)

The Argonne Heavy Water Reactor (CP-3 Prime)

The following document provides figures with all information that describe the heavy water moderated chain reacting pile at Argonne National Laboratory.
Date: August 10, 1951
Creator: Zinn, Walter H.
Object Type: Report
System: The UNT Digital Library
Boiling Reactors: A Preliminary Investigation (open access)

Boiling Reactors: A Preliminary Investigation

Technical report detailing kinetic equations that have been developed for a boiling-type reactor and inherent reactor stability studies that have been made on the basis of these equations. Presents features of the proposed reactor, comparisons of circulating types, investigations of bubble-rise velocities, effects of transient conditions of vapor mass in steam chest, and bubble time delay functions yield favorable results. [From Abstract]
Date: December 12, 1951
Creator: Stein, J. M. & Kasten, P. R.
Object Type: Report
System: The UNT Digital Library
Bronze Furnace History 313 Building (open access)

Bronze Furnace History 313 Building

This study was started in May 1949 to find methods of reducing the number of element failures in the salt bath bronze furnaces. Determining the cause of the failure and methods of eliminating them is followed to completion.
Date: February 6, 1951
Creator: Correy, Thos. B.
Object Type: Report
System: The UNT Digital Library
Calcining-Amenability Testing of Rand Precipitates (open access)

Calcining-Amenability Testing of Rand Precipitates

Test work on two samples of high-grade Rand uranium precipitate indicated the desirability of calcining it at 400' to 500'C. to cut shipping costs and provide a refinery feed quite amenable to treatment by the nitric acid digestion-TBP process.
Date: November 26, 1951
Creator: Bloecher, F. W.
Object Type: Report
System: The UNT Digital Library
Calculated thermal conductivities of pure gases and gaseous mixtures at elevated temperatures (open access)

Calculated thermal conductivities of pure gases and gaseous mixtures at elevated temperatures

From summary: "A method of calculating thermal conductivities of gases and mixtures of gases at elevated temperatures is presented. Results for carbon dioxide, helium, neon, nitrogen, and their binary mixtures are given for the temperature range of 273 degrees Kelvin to 800 degrees Kelvin. The calculated results for the pure gases are in agreement with the known experimental data."
Date: 1951
Creator: Wright, J. M.
Object Type: Report
System: The UNT Digital Library
Calculation of k-o in a Uranium-Graphite Lattice (open access)

Calculation of k-o in a Uranium-Graphite Lattice

Since the 25 content of the uranium to be used in a MTA multiplying lattice is quite uncertain at present, it is necessary to assume various degrees of depletion in order to estimate the multiplication constant K-o and the production of 49 in an infinite uranium-graphite lattice
Date: February 8, 1951
Creator: Adelman, F.
Object Type: Report
System: The UNT Digital Library
Calculation of Shielding for Mark II Accelerator (open access)

Calculation of Shielding for Mark II Accelerator

The proper roof thickness to correspond with a given side wall thickness has been estimated fro experience with the 184 feet cyclotron, which has indicated that a roof of about 1 1/2 feet should accompany a wall of 5 feet, and a roof of 4 feet should accompany a wall of 15 feet. For the roof area involved, this should bring about the condition that down-scattered neutrons in the working areas are but a small fraction of the neutrons coming through the side walls.
Date: June 30, 1951
Creator: Moyer, B. J.
Object Type: Report
System: The UNT Digital Library
Calibration of the 305 pile for graphite testing (open access)

Calibration of the 305 pile for graphite testing

From summary: "The methods of calibrating the 305 pile for impurities and density differences in graphite are reviewed and calibration constants are calculated theoretically."
Date: January 8, 1951
Creator: Duvall, George E.
Object Type: Report
System: The UNT Digital Library
Calorimetric Calibration of a Graphite Walled, Cavity-Type Ionization Chamber (open access)

Calorimetric Calibration of a Graphite Walled, Cavity-Type Ionization Chamber

Technical report outlining cavity-type ionization chambers with graphite walls that are used to measure heat dissipation in the graphite reflector of the MTR mock-up. Studies the relationship between the ionization occurring in the chamber and the heat generated in the surrounding graphite medium. [From Abstract]
Date: January 23, 1951
Creator: Jenks, G. H.; Breazeale, W. M. & Hairston, J. J.
Object Type: Report
System: The UNT Digital Library
Canning depleted uranium : production test 313-110-M, final report (open access)

Canning depleted uranium : production test 313-110-M, final report

From summary: "Uranium billets deficient in U235 were subjected to the normal successive steps in the slug fabrication process; viz., rolling, machining, and canning. No unusual behavior was observed at any point in the process, thus indicating that the depleted metal from the standpoint of mechanical properties can be considered equivalent to normal uranium."
Date: March 27, 1951
Creator: Jones, T. S.
Object Type: Report
System: The UNT Digital Library