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The Chemical Engineering of the Radium Process : Final Report

Description: Radium which occurs with the uranium in pitchblende ores remains with the gangue when the uranium is extracted by a hot, mixed acid leach. Upon completion of the laboratory research on the radium process, this report was organized into three phases which are contained in this publication.
Date: unknown
Creator: Hawlings, H. L.
Partner: UNT Libraries Government Documents Department
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Proposed R.F. Buncher for A-12

Description: A buncher and pre-accelerator for A-12 is described that has 360 degree acceptance and could handle a current of one ampere from a low voltage source.
Date: June 25, 1952
Creator: Colgate, S. A.
Partner: UNT Libraries Government Documents Department
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Ozone and Nitrogen Oxide Production by Irradiation of Air

Description: In regard to the production of ozone and various nitrogen oxides in air by action of x-rays or gamma rays, thre seems to be no direct experimental data which can be used. There is some data on the action of alpha particles on air and some on the action of cathode rays.
Date: December 21, 1950
Creator: Newton, A. S.
Partner: UNT Libraries Government Documents Department
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A Low Voltage Ion Source

Description: Describes the investigation of a particular method of extracting ions from an arc. Experimental results of a low extraction voltage ion source are given in some detail.
Date: July 12, 1951
Creator: Foster, J. S., (John Stuart), 1890-1964 & Martina, Eugene F.
Partner: UNT Libraries Government Documents Department
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Technical Activities Report for April 1953

Description: Two xenon extraction runs were made this month. It appears that a small design change in Trap #2 will be necessary so that a dry ice-trichloroethylene slurry can be used for coolant rather than liquid freon. For each of the runs this month the enriched generator was exposed for four hours in the est pile operating at 100 watts. A period of eight hours for cooling and xenon builidup was allowed before the collection and separation runs were started.
Date: May 4, 1953
Creator: Faulkner, J. E.; Davenport, D. E. & Duvall, G. E.
Partner: UNT Libraries Government Documents Department
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The Identification of the Angular Inclusions Present in Rolled Uranium

Description: Hanford uranium contains minute angular inclusions which affect the microstructure, reactivity, and other important factors controlling the serviceability of the metal. Small quantities of the inclusions have been isolated by chemical means, and the x-ray diffraction patterns and chemical analyses of the isolated materials have been determined. As a first step in the identification of the inclusions present in rolled uranium, a search was made for a chemical method of separating the inclusion… more
Date: May 15, 1953
Creator: Scott, F. A.
Partner: UNT Libraries Government Documents Department
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Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3

Description: This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).
Date: June 14, 1960
Creator: Amos, L. C.; Kirkendall, B. E. & Adler, K. L.
Partner: UNT Libraries Government Documents Department
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Removal of Graphite from Aluminum Surfaces

Description: The first of two general methods are discussed based on the removal of the thin layer of aluminum to which graphite adheres. Two electro-polishing techniques, an electrolytic etch, an anodization-deanodication cycle and two chemical etches are described.
Date: June 30, 1953
Creator: Dillon, R. L. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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The Spectrophotometric Determination of Boron in Plutonium Using an Oxalate Separation

Description: An improved method for the determination of boron in plutonium is reported. Precipitation of plutonium (III) acid oxalate prior to color development with curcumin results in increased precision, greater speed, and lower costs. Results are presented of a statistical study involving all variables.
Date: June 25, 1953
Creator: Newell, Donald M.
Partner: UNT Libraries Government Documents Department
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Spectrographic Analysis of Plutonium by the Thenoyltrifloroacetone Extraction Method

Description: Impurities are separated from plutonium solutions by means of TTA (thenoyltrifluoracetone) extractions. Plutonium in hydrochloric acid solution is reduced to the trivalent state with hydroxylamine, and some impurities are extracted into hezone or a solution of TTA in hezone. The organic phase is removed, and the plutonium in the aqueous phase is oxidized to the tetravalent state with nitric acid. Investigations of several variables which affect the extraction are described..
Date: June 29, 1953
Creator: Van Tuyl, H. H.
Partner: UNT Libraries Government Documents Department
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Monitoring Thermal and Resonance Neutron Flux

Description: The monitoring of thermal and resonance neutron flux in a thermal reactor having high flux over periods of time from 1 to 12 months using think Co foils is considered. Special attention is paid to the many correction factors to be applied to the activation data; neutron temperature, effective cadmium cutoff energy, burnout of Co59 and Co60, and decay of Co60. Results on a homogeneity test of 10 mil, 0.08% Co-A1 alloy foils is given.
Date: August 17, 1953
Creator: Heineman, R. E.
Partner: UNT Libraries Government Documents Department
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Radiological Sciences Department: Quarterly Progress Report, Research and Development Activities, July-September, 1953

Description: This is the sixteenth quarterly report of the research and development activities of the Radiological Sciences Department, Hanford Atomic Products Operation, as before, includes some items charged to control but included for general interest. Such are identified as "not charged to research."
Date: October 2, 1953
Creator: Parker, H. M.
Partner: UNT Libraries Government Documents Department
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Wet Fluoride Studies: Calcium Plutonium (IV) Fluoride

Description: Laboratory studies have shown that the double salt, CaF2-PuF4, can be precipitated by rapid addition of hydro-fluoric acid to solutions containing 25 to 75 g Pu/1, caleium equimolar to plutonium, and 1 to 10 M HNO3. The precipitate, which is subsequently washed with water and dried to 300 degrees C in dehumidified, deoxygenated argon, can be reduced thermally by calcium to give high yields of plutonium metal.
Date: December 22, 1953
Creator: Branin, P. B.
Partner: UNT Libraries Government Documents Department
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Corrosion Effects of Lowering the pH in TBP Waste Storage Tanks

Description: Large savings in waste storage space may be realized by lowering the pH at which TBP waste is stored. Additional savings in neutralizing chemicals and operating time would also increase the monetary gain from such a process change. However, before such a change could be made, the corrosive effect of TBP waste at a lower pH on the mild steel waste storage tanks had to be determined.
Date: April 6, 1954
Creator: Groves, N. D.
Partner: UNT Libraries Government Documents Department
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The Hydrogen Content of Fabricated Uranium

Description: The hydrogen contents of several types of fabricated uranium have been determined by a vacuum method and expressed in terms of ccH2/ccU. The data indicate that alpha-rolled metal contains about 0.25 ccH2(STP)/ccU whereas beta heat-treated uranium yielded values between 0.30 and 0.37 cc per cc. Restricted efforts were made to determine where in the heat treatment the 5 to 10 cc of hydrogen per slug were taken up. It appears that no one operation is wholly responsible for this additional gas, … more
Date: November 30, 1953
Creator: Ray, W. E. & Bowen, H. C.
Partner: UNT Libraries Government Documents Department
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Plutonium Trichloride: Preparation by Reaction with Phosgene or Carbon Tetrachloride and Bomb Reduction to Metal

Description: Thirty gram patches of plutonium dioxide can be readily chlorinated by reaction with phosgene or carbon tetrachloride at temperatures of 350 and 450 C respectively. Plutonium trichloride prepared by either method can be reduced to the metal in a hermetically sealed bomb by reaction with calcium. On a twenty gram scale yields of approximately 97 per cent are obtained when a calcium-iodine booster is employed. It has been demonstrated that a method for reduction of plutonium trichloride to the… more
Date: December 3, 1953
Creator: Tolley, W. B.
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report June - September 1963

Description: Introduction: The objective of Project Agreement 22 is to determine the feasibility of covering the complete reactor neutron flux start range from 10(3) - 5 x 10(13) nv by using in-core chambers. The counting mode of operating will be used at low neutron fluxes and the root mean square voltage fluctuation mode will be used at high neutron flux levels. Experiments have been run utilizing various ion chambers, gases, gas pressures, voltage, and cables to measure sensitivities and range operating … more
Date: October 1963
Creator: DuBridge, R. A.
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report September - December 1963

Description: Introduction: The objective of Project Agreement 22 is to determine the feasibility of using in-core ion chambers to cover the complete reactor neutron flux startup range from 10(4) -5 - 10(13) nv using in-core ion chambers. The counting mode of operation will be used at low neutron flux levels and the RMS voltage fluctuation mode (Campbell Theorem) will be used at high neutron flux levels. The June-September Progress Report (GEAP-4386) shows how the RMS voltage mode can be used, discusses c… more
Date: January 1964
Creator: DuBridge, R. A.
Partner: UNT Libraries Government Documents Department
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Mechanical, Fluid Flow, and Heat Transfer Out-Of-Pile Tests on EVESR MKI Prototype Fuel Bundle

Description: Summary: An EVESR MKI prototype fuel bundle was fully instrumented and operated intermittently for a 5-month period at the Pacific Gas and Electric Company’s Moss Landing Power Station. The vessel was operated up to 1000 psi with steam flows from 3000 to 26,600 lb/h, and steam inlet temperatures up to 825 degrees F. Data was recorded for blowout, vibration, flow distribution, heat transfer and pressure drop. The mechanical integrity of the fuel bundle, riser, and jumper system was satisfact… more
Date: February 1964
Creator: Polomik, E. E.; Fritz, J. R. & Ianni, P. W.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Eighteenth Quarter, November, 1963-January, 1964

Description: From introduction: "This is the eighteenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Date: February 15, 1964
Creator: Flock, W. L. & Imhoff, D. H.
Partner: UNT Libraries Government Documents Department
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Preoperational Power Stability Analysis of the Consumers Big Rock Point Plant

Description: Summary: An analytical study of the stability of the Big Rock Nuclear Reactor has been performed for the plant as built, and supplements a previous design stability study. The plant has been determined by this analysis to be very stable under every mode of operation anticipated during Phase I of the development program testing. Even under conservative assumptions of system parameters the minimum calculated gain and phase margins do not go below 13.0 db and 46 degrees, respectively. (Nor are … more
Date: February 1964
Creator: Case, J. M.
Partner: UNT Libraries Government Documents Department
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Two-Phase Pressure Losses Quarterly Progress Report: Eighth Quarter, November 12, 1963 - February 11, 1964

Description: Technical report describing that voids were measured in a ½-inch by 1-3/4-inch channel with the S-1 insert (B(0)/B(1) = 0.4, L(0) = 0.1 inch), at 2 inches ahead of the insert (position A), ½-inch past the insert (position B), 5 inches past (position C), and 12 inches past (position D). The conditions were: P – 1000 psia, G = 1.00 x 10(6) lb/h-ft(2), and x = 18.8 percent. Average void and void distribution at position A are the same as for flow in a straight channel. Void distribution at posi… more
Date: March 1, 1964
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
Partner: UNT Libraries Government Documents Department
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High Power Density Development Project: Sixteenth Quarterly Progress Report, January-March 1964

Description: Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC. Five tasks are in progress: (1) Task 1A-High Power Density Fuel Development, (2) Task 1B-Fuel Fabrication Development. Assembly, (3) Task II-Stability, Heat Transfer and Fluid Flow, (4) Task III-Physics Development, and (5) Task IV-Co-Ordination and Test Planning.
Date: April 1, 1964
Creator: Holladay, R. L.
Partner: UNT Libraries Government Documents Department
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