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Metallurgy Division Quarterly Progress Report for Period Ending October 31, 1950

Description: Technical report outlining the rate of production of modified MTR type fuel elements for the Bulk Shielding Facility has proceeded. Includes compatibility test that were started as a guide in the selection of materials suitable for fuel-element fabrication. [From Summary]
Date: February 8, 1951
Creator: Frye, J. H.; Miller, E. C. & Bridges, W. H.
Partner: UNT Libraries Government Documents Department
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Forced Convection Heat Transfer in Thermal Entrance Regions Part III. Heat Transfer to Liquid Metals

Description: Technical report covering the work done to explore heat transfer analytically and experimentally in liquid metals in turbulent flow within the thermal entrance region of circular tubes having uniform well temperature. Includes implications of this research. [From Summary]
Date: June 25, 1954
Creator: Harrison, William B.
Partner: UNT Libraries Government Documents Department
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Studies on the Removal of Radioisotopes From Liquid Wastes by Coagulation

Description: Technical report covering work completed on the removal of radioisotopes from water using a calcium phosphate floc as a carrier. This research was performed as part of the Health Physics Waste Disposal Research Section work on the removal of small quantities of radioactivity from large volumes of water. [From Abstract]
Date: January 23, 1951
Creator: Lauderdale, Robert A., Jr.
Partner: UNT Libraries Government Documents Department
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The Corrosion of Hot-Pressed, Extruded, and Vacuum Cast Beryllium in Simulated Cooling Water for the Materials Testing Reactor

Description: Technical report covering the technology of hot-pressed beryllium production and its rapid advancement toward the end of 1949. Part I is devoted to corrosion studies made on hot-pressed and vacuum cast extruded metal which was considered representative of production. Part II is concerned with the results of tests made on special cast and hot-pressed beryllium which contained added impurities. [From Introduction]
Date: January 9, 1953
Creator: Reed, James
Partner: UNT Libraries Government Documents Department
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Evaluation of Alternate Solvents for Diethyl Ether in the Extraction of Uranium From Mallinckrodt Type Ore Feeds

Description: Technical report evaluating solvents for use in the extraction of uranium from Mallinckrodt type ore feeds. Re-evaluates the Mallinckrodt process in the light of the more recent solvent extraction development that has been carried out at various AEC sites.
Date: November 6, 1950
Creator: Runion, T. C.
Partner: UNT Libraries Government Documents Department
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Classified Progress Report of the Reactor Science and Engineering Department; April 1 - June 30, 1950

Description: Technical report outlining the progress of reactor completion and startup events by the Reactor Theory, Physics, Radioisotope Development, Geology, Meteorology, Waste Concentration, and Waste Disposal groups in the Reactor Science and Engineering Department of Brookhaven National Laboratory.
Date: 1950
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department
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Preliminary Study of a Uranium - Bismuth Liquid Fuel Power Reactor L. F. R . 2

Description: Technical report and preliminary design calculations describing a type of liquid fuel reactor adaptable for production or breeding on a U-233 cycle based on data at Brookhaven National Laboratory. Describes design calculations for generating significant amounts of power and neutrons by use of uranium-bismuth solutions with fused salts in the reactor system.
Date: April 27, 1951
Creator: Gurinsky, D. H.; Kaplan, I.; Miles, F. T.; Williams, C. & Winsche, W. E.
Partner: UNT Libraries Government Documents Department
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A Continuous Fission Product Separation Process; I. Removal of the Rare Earths (Lanthanum Cerium, Praseodymium, and Neodymium) From a Typical Liquid Bismuth-Uranium Reactor Fuel by Contact with Fused LiCl-KCl Mixtures

Description: Technical report investigating the distribution of rare earth elements between a liquid bismuth-uranium solution and fused KCI-LiCi mixtures. Report warrants further research on the liquid bismuth-uranium-fused salt system due to the benefit of continuous fission removal processes.
Date: July 1, 1951
Creator: Bareis, D. W.
Partner: UNT Libraries Government Documents Department
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Progress Report of Reactor Science and Engineering Department; July 1 - September 30, 1951

Description: Technical report covering the classified tests on two types of nuclear reactors of the Department of Reactor Science and Engineering. Outlines tests on heat transfer and hydraulics, fabrication and corrosion studies on the normal water.
Date: 1951
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department
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Plate Efficiency in the Exchange of Deuterium Between Ammonia and Hydrogen

Description: Technical report outlining measurements of the equilibrium in the exchange of deuterium between ammonia and hydrogen and of the kinetics of this reaction. Details a series of tests carried out to measure Murphree plate efficiencies.
Date: December 3, 1951
Creator: Perlman, Morris L. & Bigeleisen, Jacob
Partner: UNT Libraries Government Documents Department
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A Manual of HRE Control and Instrumentation

Description: Technical reports outlining the controls for the Homogeneous Reactor Experiment (HRE); controls are divided into three principal groups. 1. Reactor. 2. Process or auxiliary. 3. Power generation. These are the classifications designating the primary functions of the controls. [From Introduction]
Date: January 23, 1952
Creator: Quarles, L. R. & Walker, W. P.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Progress Report for Period Ending July 31, 1951

Description: Technical report outlining the effect of strain rate on the tensile properties of thorium. It has been found that the yield strength increases slightly with increasing strain rate, and that tensile strength increases but to a less extent. Studies on the fabrication of thorium by extrusion and drawing have continued, as have studies on the extrusion cladding of thorium and uranium with zirconium. [From Summary}
Date: February 6, 1952
Creator: Miller, E. C. & Bridges, W. H.
Partner: UNT Libraries Government Documents Department
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Surface to Mass Dependence of Effective Resonance Integrals for Uranium 238 Cylinders

Description: Technical report outlining the determination of the effective resonance integral for U238 as a function of the mass ratio for cylinders of 5/8" to 3" diameter. Also gives a linear approximation of the effective resonance integral with infinite shielding in the form of a function. [From Abstract]
Date: March 20, 1951
Creator: Risser, J. R.; Arfken, G. B., Jr.; Cuykendall, T. R.; Stephenson, R. J. & Caldwell, D. O.
Partner: UNT Libraries Government Documents Department
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A Solvent Extraction Method for Neptunium (237) Analysis

Description: Technical report describing a rapid and quantitative radiochemical method for the analysis of neptunium (237). This method is based on the extraction of neptunium (IV) with thenoyl-trifluoracetone in xylene. Neptunium (237) is separated free from other alpha emitters and from non-radioactive interferences, and the method may be readily adapted to remote control. [From Abstract]
Date: July 10, 1951
Creator: Moore, Fletcher L.
Partner: UNT Libraries Government Documents Department
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