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13-Watt Curium-Fueled Thermoelectric Generator for Hard Lunar Impact Mission. Final Report-Subtask 5.8

Description: Results of a conceptual design study for a curium powered thermoelectric generator of minimum size and weight which is capable of sustaining hard impact is presented. The generator produces a minimum of 13 watts of d-c power at 3 volts, and weighs 6.2 pounds excluding shielding. (J.R.D.)
Date: August 1, 1960
Creator: Bloom, J. L.
Partner: UNT Libraries Government Documents Department
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300,000-KWE SGR Nuclear Power Plant of Current Technology

Description: Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
Date: August 1, 1960
Creator: Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
Partner: UNT Libraries Government Documents Department
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Analysis of Nucleon-Nucleon Scattering Experiments

Description: Presented at session S-1 of the Tenth Annual International Conference on High-Energy Physics, Rochester, New York, August 25- September 1, 1960. The analysis of the latest experiments on p-p scattering at 210 Mev makes it probable that there is a unique set of phase shifts at this energy. Under reasonable assumptions about continuity of the phase shifts and the behavior of the higher partial waves, it is possible to pick a unique solution also at 310 and 95 Mev. This opens a new era in the anal… more
Date: August 1960
Creator: Noyes, H. Pierre.
Partner: UNT Libraries Government Documents Department
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Annual Summary Research Report in Engineering for July 1, 1959-June 30, 1960

Description: Work was continued on the determination of size and distribution of dispersed phase droplets in a pulse column. The droplet behavior and dispersed phase hold-up in Yorkmesh packing was studied with an equilibrated system of methyl isobutyl ketone and water with the ketone phase dispersed. An investigation is being made of the recovery of copper and EDTA from rare-earth ion exchange wastes. The effect of vapor properties on entrainment from bubble cap trays is being investigated. The design, con… more
Date: August 1, 1960
Partner: UNT Libraries Government Documents Department
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Bibliography of SNAP Reports

Description: A listing is presented of documents, films, slides, and those items which were formally produced for utilization by the AEC concerning the SNAP project. (J.R.D.)
Date: August 1, 1960
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Control Rod Drive Line Testing

Description: The adequacy of the Consolidated Edison Thorium Reactor (CETR) control rod drive line operation was evaluated and proven by the development program described in this report. This program also included evaluation of materials and fabrication processes.
Date: August 1960
Creator: Good, J. A. & Thoren, D. E.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Control System Design

Description: The Consolidated Edison Thorium Reactor Control System has been designed to provide the operators with a reliable, safe and accurate means of controlling the plant. Manual and automatic positioning of control rods can be accomplished. The automatic plant controller has been designed to meet the design criteria under the representative CETR demanded load changes. Adaptability has been built into the plant controller by providing variable controller adjustments for variations in reactor charac… more
Date: August 1960
Creator: Carson, W. E.; Chubb, W. B.; Pickett, R. T. & Deddens, J. C.
Partner: UNT Libraries Government Documents Department
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Corrosion Product Activity Distribution Across the Chemical Process System in the Consolidated Edison Thorium Reactor Plant

Description: A study has been performed to determine the corrosion product and water impurity activities in the CETR Chemical Process System. A simplified mathematical model is used to represent the physical situation; however, the magnitude of the activities, taken at the end of the core life to represent the most conservative case, is considered sufficiently accurate for engineering calculations.
Date: August 1960
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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CREEP AND CORROSION PROPERTIES OF ZIRCALOY-2 IN STEAM AT 750 F

Description: Test equipment to determine the creep properties of Zircaloy-2 in a 750 deg F 500-psi steam atmosphere was designed and constructed. Duplicate tests were performed at stresses to produce failure in approximately 1, 10, 100, and 1000 hr. A comparison between these data and data obtained in vacuum-test equipment showed that a corrosive test atmosphere does not alter ductility or failure times appreciably. (auth)
Date: August 1, 1960
Creator: Jablonowski, E. J. & Shober, F. R.
Partner: UNT Libraries Government Documents Department
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Design of the Movable and Fixed Control Components for the Consolidated Edison Thorium Reactor

Description: Prototype testing and thorough design analyses have proven the control components for the Consolidated Edison Thorium Reactor are adequate to withstand loads imposed during operation and handling. Assumptions made in the design analyses and cycles run during prototype testing subjected the components to more rigid conditions that are anticipated during actual operation. Results indicate the control components meet their design requirements.
Date: August 1960
Creator: Gestson, D. K.; Collings, D. M. & Maynard, W.
Partner: UNT Libraries Government Documents Department
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Development of a Fuel-Element Leak-Detection System Based on the Principle of Isotopic Exchange

Description: The selective removal of halide fission products from an aqueous solution by exchange with the halide in a solid silver halide was studied as the basis for a fuel-element leak detector. The retention of fission-product halides on a silver halide column was investigated as a function of coolant flow rate, halide anion, and column size. Fission prcduct decontamination factors and predicted operating lifetimes were obtained for a number of reactor operating conditions. It is concluded that a sensi… more
Date: August 1, 1960
Creator: Howes, J. E., Jr.; Elleman, T. S. & Sunderman, D. N.
Partner: UNT Libraries Government Documents Department
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Development of Corrosion-Resistant Alloys for Use as Container Materials for Decladding Solutions or as Welding Alloys

Description: Twenty-four experimental alloys were developed and evaluated as container materials or welding alloys for use with Sulfex and Niflex decladding solutions. Niflex solutions which were more corrosive than Sulfex solutions to most of the experimental alloys, produced severe localized attack on weldments made on vacuum-melted Hastelloy F with the experimental alloys. However, several of the alloys, when self-welded, were not selectively attacked. Some of these showed a substantial improvement in re… more
Date: August 1, 1960
Creator: Peterson, Charles L.; Drennen, David C.; Langston, Merritt E.; Hall, A. M. & Boyd, Walter K.
Partner: UNT Libraries Government Documents Department
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An Electron Multiplier as a Detector for a Surface Ionization Mass Spectrometer--Design

Description: A description of a 14-stage electron multiplier for use amplifying the detector signals in a surface ionization mass spectrometer is given. The system can either measure the multiplier anode current or count the anode pulses. Pulse counting may be used for- signal currents in the range from lO/sup -13/ to 10/sup -18/ amp. The range of the normal electrometer circuit is extended by the electron multiplier so that it measures currents from l0/sup -10/ to 10/sup -15/ amp with a fast response. (aut… more
Date: August 1, 1960
Creator: Cathey, L.
Partner: UNT Libraries Government Documents Department
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Fast Fuel Test Reactor - FFTR Conceptual Design Study

Description: Report describing the design of a Fast Fuel Test Reactor (FFTR), analyses of of the reactor's operations, related costs, and possible future projects.
Date: August 1960
Creator: Brubaker, R.; Hummel, H. H.; McArthy, A.; Smaardyk, A. & Kittel, J. H.
Partner: UNT Libraries Government Documents Department
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FAST FUEL TEST REACTOR-FFTR CONCEPTUAL DESIGN STUDY

Description: The Fast Fuel Test Reactor (FFTR) is a nuclear facility for the purpose of irradiating samples of fuels and structural components for use in fast reactors. The core consisis of a plate type element in a square configuration. Beryllium metal between the fuel elements is used to obtain a neutron energy spectrum in the hard intermediate region. Cooling of the core and test specimens is accomplished by means of liquid sodium. The design concept was carried through in sufficient degree in the follow… more
Date: August 1960
Creator: Brubaker, R.; Hummel, H. H.; McArthy, A.; Smaardyk, A. & Kittel, J. H.
Partner: UNT Libraries Government Documents Department
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The Fluorination of Uranium From Dried Solids and Its Application to the Fluoride Volatility Process

Description: The fluorination of uranium from dried solids representative of those obtained from the fluid-bed drying of dissolver solutions of high zirconium alloy fuels. e.g.. Dresden and Army Package Power Reactor fuels, was studied under a variety of conditions. Variables investigated were particle size, additives, temperature, time. hydrofluorination, and pyrolysis. Temperatures in excess of 650 deg C were needed to ensure complete removal of uranium from the solid. Pyrolysis with HF of previously fluo… more
Date: August 1, 1960
Creator: Johnson, C. E. & Fischer, J.
Partner: UNT Libraries Government Documents Department
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Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory

Description: Report that summarizes the potential hazards of the Hanford Critical Mass Laboratory and presents operation procedures which will limit the probability of a nuclear accident. The report also outlines the planned experimental program, descriptions of the facility, and the administration of nuclear safety in the laboratory.
Date: August 1, 1960
Creator: Reardon, W. A.; Clayton, E. D.; Brown, C. L.; Masterson, R. H.; Powell, T. J.; Richey, C. R. et al.
Partner: UNT Libraries Government Documents Department
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Heavy Water Power Reactor Program Monthly Report: August 1960

Description: Report documenting progress on the Heavy Water Power Reactor Program including progress made in the physics, engineering, metallurgy, and nuclear development programs.
Date: August 1960
Partner: UNT Libraries Government Documents Department
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High Temperature Cladding Alloys

Description: For high-temperature applications, fuel element cladding materials are required to protect the base metal structure and to contain the fuel so as to minimize fission product release and fuel loss. Since the early work on clad Mo fuel element concepts, many metallic cladding systems have been investigated for direct cycle reactors. The developments in stainless steel and Ni alloy claddings are reviewed and the more recent applications of new oxidation- resistant ferrous-base and chromium-base al… more
Date: August 1960
Creator: Collins, J. F. & McGurty, J. A.
Partner: UNT Libraries Government Documents Department
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Irradiation Test Program for the Consolidated Edison Thorium Reactor

Description: The Irradiation Test Program for the Consolidated Edison Thorium Reactor was conducted to obtain confirmation of the stability and performance of the reference fuel element materials and of test assemblies under design operation conditions. The irradiated specimens were tested to determine mechanical properties and corrosion resistance to borated water.
Date: August 1960
Creator: Baker, P. B.; Dzura, E. J. & Johnson, C. R.
Partner: UNT Libraries Government Documents Department
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