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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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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, construction, and operation of forced convection loops for circulating liquid metals are reported. The corrosion of 430 stainless steel and 21/2% Cr-l% Mo steel by a liquid lead- bismuth eutectic is reported. The operation of a stainless-steel sodium-cooled liquid-metal condenser is described. The effect of ten additives, including V, Mg, Zr, and Ce in inhibiting the corrosion of stainless steel by lead-bismuth eutectic is being investigated. The current process for preparation of sodium ethyl sulfate is given. Single crystals of Zn, Sn, Pb, and AgCl were grown with a simple, low cost, Bridgman-type crystallizer. Tests were performed at 800 to 1000 deg C on Y, Nb, and Ta loops, circulating Th-Mg and U-Cr eutectics. Work on the development of electromagnetic pumps is reported. A new technique was developed for applying an impervious coating of glass to yttrium. (For preceding period see IS-16.) (W.L.H.)
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 characteristics. Extensive analog studies have been made of the various plant parameters and their effect on control was carefully evaluated. These analog studies have shown that the control system will perform in a satisfactory manner under the most adverse plant conditions.
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 sensitive, rapid leak detector for a water- cooled reactor could be constructed from a silver bromide or iodide column monitored by a neutron detector to detect delayed neutrons from the halide fission products. The feasibility of gross gamma monitoring was found to be dependent upon the intensity of the gamma background arising from absorbed fission products on the silver halide column. (auth)
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 resistance to the decladding solutions. The most promising alloys were based on either 45 wt.% nickel--22 wt.% chromium or 50 wt.% nickel--25 wt.% chromium, with at least 6 wt.% molybdenum, and 1 wt.% titanium, 0.6 wt.% manganese, 0.4 wt. % silicon, 0.02 wt.% carbon, and the balance, iron. The alloy most resistant to both solutions contained 6 wt.% molybdenum and 1 wt.% copper in the 50 wt.% nickel--25 wt.% chromium base. Its corrosion rate of 22 mils per month in Niflex, with no selective attack, was significantly lower than the 105 mils per month recorded for Hastelloy F. Even lower rates would be expected under the less stringent conditions of actual process operation. Indications are that more resistance might be obtained by increasing the chromium and nickel contents. (auth)
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. (auth)
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 following areas of preliminary concern: number and size of irradiation facilities, sample power requirements, plant layout to evaluate site requirements, plant and nuclear design parameters to evaluate essential equipment requirements. plant-capital-cost estimate, annual- operating-cost estimate, and estimate of construction time schedule. (W.D.M.)
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 fluorinated materials aided in uranium removal from the zirconium solid. (C.J.O.)
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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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 alloys as claddings for refractory metals are presented. (auth)
Date: August 1, 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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LOGARITHMIC SPIRAL LIGHT PIPE FOR SCINTILLATORS

Description: A prccedure is described for designing and making logarithmic spiral light pipes which are to be used in coupling scintillators to photomultipliers in cases where the scintillator must be placed in a strong magnetic field. (C.J.G.)
Date: August 1, 1960
Creator: Kaiser, W.C.; MacKay, A.J. & Managan, W.W.
Partner: UNT Libraries Government Documents Department
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Low Noise Amplifiers for Use with Solid State Detectors

Description: Abstract: This report summarizes data developed at the Instrument and Controls Division, Oak Ridge National Laboratory on low noise amplifiers used with solid state detectors.
Date: August 1960
Partner: UNT Libraries Government Documents Department
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