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Homogeneous Circulating Fuel Reactor Power Plant: Conceptual Design Study Report

Description: The purpose of this report is to present a conceptual design study on a low power electrical and heat generating plant powered by nuclear energy. The nuclear reactor used in this study is the homogeneous circulating fuel type.
Date: May 31, 1955
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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Recovery of Uranium From Congo Leach Liquors With Ion Exchange Resins

Description: A method is described for recovery of uranium from sulfuric acid leach liquors of Congo ores using anion exchange resins. Excellent uranium recoveries were obtained in cyclic tests which indicate uranium capacities of 11 to 26 lbs. of U3O8 per cubic foot of resin per day. Preliminary tests indicate that sulfuric acid may be as effective as hydrochloric acid in providing the required acidity in the eluant.
Date: October 31, 1951
Creator: Kennedy, Richard H. & Howland, Frederick A.
Partner: UNT Libraries Government Documents Department
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Application of Heavy Media Separation, Flotation and Carbonate Leaching to Congo Ores

Description: 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.
Partner: UNT Libraries Government Documents Department
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A Proposal For Reducing Impurities in a Stabilized Pinched Discharge

Description: It is proposed to reduce the initial wall hangup and consequent plasma contamination of a stabilized pinched discharge by reducing the Bz pressure difference across the current sheath to nearly zero at early times. Two methods for accomplishing this are proposed, both involving multistage programming of the Bz system.
Date: July 31, 1957
Creator: Lovberg, Ralph H. (Ralph Harvey)
Partner: UNT Libraries Government Documents Department
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Monex Process: Terminal Report

Description: Chemical and engineering data were obtained for the feed digestion system and the extraction-scrub step of the Monex tributyl phosphate solvent-extraction process for recovering thorium and uranium from nitric acid-digested unclarified monasite sludge. Tests of the recommended conditions in a 2-in.-dia pulsed column demonstrated that thorium losses were approximately 1.2% and uranium losses, 1.5%. The flowsheet is workable but is not necessarily optimum.
Date: January 31, 1958
Creator: McNamee, R. J. & Wischow, R. P.
Partner: UNT Libraries Government Documents Department
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Technical Discussion of Brookhaven Off-Site Personnel Monitoring Service

Description: A number of questions have arisen in regard to the interpretation of personnel monitoring results reported to users of the Brookhaven neutron monitoring service. The original announcement was rather brief and did not contain most of the technical characteristics upon which an evaluation of results must be based. The following paragraphs have been composed with the hope that they will clarify the meaning of the exposure reports.
Date: July 31, 1953
Creator: Cowan, F. P.
Partner: UNT Libraries Government Documents Department
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New Production Reactor Thermal Shielded Studies

Description: The relative neutron capture gamma production in several prospective iron thermal shielding materials for the New Production Reactor was measured to determine the merit of adding boron to the metal. It was found that for the beam geometry the used addition of 1 1/2 percent boron to the iron before casting reduced the soft gamma production by a factor of 6.5 and the hard gamma production by a factor of 10. No attempt was made to measure gamma or neutron transmissions.
Date: August 31, 1959
Creator: Friesenhahn, S. J.
Partner: UNT Libraries Government Documents Department
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PRTR Total Energy Distribution Calculations

Description: Since the calculation of the PRTR energy distribution was first carried out by J. R. Triplett, the design has become sufficiently fixed to allow a refinement of his values. The present analysis, also, includes a calculation of the fraction of energy which is released in the shroud and process tubers that flows to the primary coolant to the top and bottom shield coolant is taken into consideration. Nuclear data used in the original calculations still appears satisfactory and is, therefore, util… more
Date: July 31, 1959
Creator: Peterson, R. E.
Partner: UNT Libraries Government Documents Department
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Correlation of Exponential and PCTR Measurements of Cluster Fuel Elements with Theory

Description: Accurate knowledge of the lattice parameters comprised in the four factor formula k∞=η∈Pi are required for optimum designing of reactors. In the special case of cluster fuel elements conventional handbook formulas are of little use. It is the intent of this paper to report the results of some recent improvements in the calculation of these parameters. By the addition of certain refinements in the calculation of these parameters. By the addition of certain refinements to the conventional calcula… more
Date: December 31, 1958
Creator: Joanou, G. D.
Partner: UNT Libraries Government Documents Department
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The Production of 320 Mev Deuterons By He3 Stripping

Description: The purpose of this report is to describe a method of obtaining deuterons from the 184-inch cyclotron of higher energy than can be achieved from direct acceleration.
Date: August 31, 1953
Creator: Ise, John, Jr.; Pyle, Robert V.; Hicks, Donald A. & Main, Robert M.
Partner: UNT Libraries Government Documents Department
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Chemistry Division Quarterly Report: September, October, November, 1952

Description: Quarterly progress report for the Chemistry Division of the University of California Radiation Laboratory: nuclear chemistry, bio-organic chemistry, metals and high temperature thermodynamics, basic chemistry, and chemical engineering.
Date: December 31, 1952
Creator: University of California Radiation Laboratory
Partner: UNT Libraries Government Documents Department
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Quarterly Report October, November and December, 1956

Description: Methods of producing extremely clean surfaces on rolled Zircaloy-2 strip have been investigated. It has been found that the finer abrasives, 400 mesh or finer, are more effective than coarse types because of their ability to penetrate pits and crevices more readily. Two such cleanings, with an intermediate 35 v/o HNO3-5 v/o HF pickle, resulted in a microscopically clean surface. Ultrasonic inspection of the EBWR fuel plates has been completed during this quarter. Approximately 95% of the plates… more
Date: December 31, 1956
Creator: Foote, Frank G.; Schumar, James F. & Chiswik, Haim H.
Partner: UNT Libraries Government Documents Department
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Calculated Pressure Drop In the 1706-KER Loop

Description: The purpose of this report is to provide calculated liquid flow pressure drop data for the 1706-KER recirculation loops.
Date: January 31, 1956
Creator: Sebade, D. E.
Partner: UNT Libraries Government Documents Department
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Process Engineering Report on Thorium Semi-Works Plant for the Feed Materials Production Center - Fernald, Ohio, Job No. 3542

Description: This technical report presents the process design for the thorium semi-works plant which will be located at the Feed Materials Production Center, Fernald, Ohio. It contains the process information required for the layout and detailed mechanical design of the thorium plant.
Date: January 31, 1952
Creator: Bulkowski, H. H.; Delaplaine, J. W.; Holby, G. V.; Natale, N. R.; Reiter, W. M. & Roe, B. J.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report January, February, and March 1954

Description: This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion.
Date: March 31, 1954
Creator: Foote, Frank G. (Frank Gale), 1906- & Schumar, James F.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report October, November, and December 1953

Description: This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion.
Date: December 31, 1953
Creator: Foote, Frank G. (Frank Gale), 1906- & Schumar, James F.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report [for] October, November, and December, 1952

Description: This quarterly progress report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses (1) water-cooled reactors, (2) liquid metal-cooled reactors, (3) reactor development - fuel metallurgy, (4) reactor development - component metallurgy, (5) basic metallurgy, (6) basic ceramics, (7) aqueous corrosion, and (8) applied metallurgy.
Date: December 31, 1952
Creator: Foote, Frank G. & Schumar, James F.
Partner: UNT Libraries Government Documents Department
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Helium Leak Detector Test for Hanford And Savannah River Fuel Slugs

Description: The Helium Leak Detector Test provides a method for detecting the presence of minute holes, cracks, fissures, etc. in the aluminum jackets of Hanford and Savannah River reactor fuel slugs which would allow moisture to penetrate to the uranium during reactor operation.
Date: December 31, 1952
Creator: Barnes, A. H.; Smith, F. A. & Wimunc, E. A.
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of West Virginia

Description: Report documenting the suitability of West Virginia for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.
Date: January 31, 1952
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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Time Dependence of the Slowing Down of Neutrons with Constant Scattering Mean Free Path

Description: Simple expression are derived for the time dependence of slowing down of neutrons in a simple media. In Section I, a method suggested by age theory is used, while in section II, a two parameter scattering function is employed. Results are compared with exact calculations.
Date: May 31, 1952
Creator: Bell, G. I. & Bethe, Hans A. (Hans Albrecht), 1906-2005
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of Utah

Description: Report documenting the suitability of Utah for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.
Date: December 31, 1951
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of New Mexico

Description: Report documenting the suitability of New Mexico for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest
Date: October 31, 1951
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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