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The X-Ray Spectra of Polonium Atomic Number 84

Description: From abstract: "Two samples, each containing an estimated 10 curies (2 mg) of polonium-210, were purified by vacuum distillation and evaporated onto oblique sections of X-ray targets made of copper. Four lines of the K series and ten lines of the L series of the X-ray spectrum of polonium were recorded with a one-meter transmission crystal spectrograph and a 25-centimeter Bragg spectrograph, respectively. Measured wavelengths agree approximately with values predicted by extrapolation of Moseley… more
Date: April 15, 1952
Creator: Peed, W. F.; Burkhart, L. E.; Staniforth, R. A. & Fauble, L. G.
Partner: UNT Libraries Government Documents Department
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The Reaction Between Hydrogen and Oxygen by Catalysis and the Thermal Reaction

Description: From abstract: "The reaction between hydrogen and oxygen with the aid of various catalysts (especially platinum on aluminua) has been studied, and the operating variables such as flow rates, space velocity, temperature, and gas composition have been examined rather extensively. It has been found that hydrogen and oxygen in stoichiometric proportions and mixed with either steam or helium may be made to react to the extent of 99.5% or greater at space velocities up to 30,000 hr-1, or even higher,… more
Date: January 15, 1952
Creator: Kuhn, D. W.; Ryon, A. D.; Palko, A. A. & Clewett, G. H.
Partner: UNT Libraries Government Documents Department
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Containment Vessel Cost and Buckling Considerations

Description: The economics of various types of reactor containment are briefly discussed. Charts [?] suitable for feasibility cost estimates are presented for spherical and cylindrical pressure vessels. Approximate limitations on cylindrical pressure vessel height imposed by buckling considerations for snow, wind and vessel weight loads are also presented.
Date: September 15, 1959
Creator: Robinson, G. C.
Partner: UNT Libraries Government Documents Department
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PRFR Pilot Plant: An Evaluation of Equipment Performance During the Processing of Irradiated Natural Uranium in April 1959

Description: The Power Reactor Fuel Reprocessing complex and the equipment performance during the processing of irradiated natural uranium fuel are described. Equipment performance was generally satisfactory for rates up to 400 kg or uranium per day. =Three cases in which equipment malfunctioning significantly affected the process, and the scheduled modifications, are discussed.
Date: September 15, 1959
Creator: Matherne, J. L.
Partner: UNT Libraries Government Documents Department
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Estimate of Potential Fuel Reprocessing, Revision #29 - Part A

Description: The power and estimated reprocessing load for existing and proposed United States and United States-built reactors of 10 Kw or greater thermal power.
Date: September 15, 1959
Creator: Ullmann, J. W.
Partner: UNT Libraries Government Documents Department
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Additional Information on Eurochemic Air Sampling System

Description: Additional information relative to the proposed Eurochemic Air Sampling System is given. The original questions are listed with the answers for convenience.
Date: September 15, 1959
Creator: Shank, E. M.
Partner: UNT Libraries Government Documents Department
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A Preliminary Study of the Dynamics of Solvent Extraction Cascades. I, Program for Digital and Analog Simulation

Description: Understanding of the dynamics of process systems usually leads to improved control. For systems of nuclear interest, the trend of improvement is likely to approach 'total automation' and computer control. To improve understanding of process dynamics in one specific field the present study is dealing with solvent extraction equipment. Specifically, mathematical models are being developed for applying both digital and analog computer to the transient behavior of extraction cascades.
Date: September 15, 1959
Creator: Updike, O. L. & Whatley, M. E. (Marvin E.), 1926-
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Fourteenth Quarter, October-December 1962

Description: From introduction: "This is the fourteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: January 15, 1963
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Thirteenth Quarter, July-September 1962

Description: From introduction: "This is the thirteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: May 15, 1963
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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Determination of Oxygen in Oxide Films by Neutron Activation Analysis

Description: Preliminary experiments have been conducted to evaluate the use of the nuclear reactions Li6 (n,α)H3 and O16(H13,n)F18 to determine the thickness of oxide films on metals. Sheets of thin paper and of aluminum, imbedded in powdered LiF, were irradiated with pile neutrons at a flux of 6 x 10^11 n/cm^2/sec and counted with an end-window proportional counter. A saturation activity of 1.87 hr F18 of 150 dis/min per microgram of oxygen was observed in the paper, but radioactivity due to impurities ma… more
Date: July 15, 1959
Creator: Winchester, J. W.; Meyer, R. E.; Bate, L. C. & Leddicotte, G. W.
Partner: UNT Libraries Government Documents Department
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Containment Properties of DCX

Description: The "absolute" containment of ions in the DCX magnetic mirror field resulting from the cylindrical symmetry of the field is discussed. The regions of confinement in space and momentum are plotted for 300 Kev deuterons.
Date: June 15, 1959
Creator: Fowler, T. K. & Rankin, M.
Partner: UNT Libraries Government Documents Department
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The Effect of Acidity and Reducing Agents on Ruthenium Solvent Extraction by Tributyl Phosphate in the 25 Process

Description: Results of tracer studies suggest that, in tributyl phosphate extraction processes designed to recover and purify fissionable material, minimum ruthenium extraction should be obtained from feeds at least 2 M in nitric acid or at least 1 M acid-deficient. Ruthenium decontamination was decreased by preheating the feed and increased by pretreatment with reducing agents. A pretreatment using 0.06 M ferrous ion and 0.5 M urea with 1 hr simmering at 85°C should increase ruthenium decontamination abou… more
Date: December 15, 1954
Creator: Flanary, J. R. & Frashier, L. D.
Partner: UNT Libraries Government Documents Department
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Electromagnetic Research Division Quarterly Progress Report: Part I for Period Ending December 31, 1951

Description: From abstract: "Operation of the 86-inch cyclotron has been continuous except for a three-day interruption caused by a water leak inside the vacuum chamber; monthly output has averaged over 210,000 [mu]a-hr; the average continuous (168-hour week) beam power has been approximately 5.5 kw; and the energy of the beam has been determined to be ~19.4 Mev. No changes due to radiation damage have been detected in Inconel tubes containing UF4-NaF-KF eutectic which were irradited in the 96-inch cyclotro… more
Date: January 15, 1952
Creator: Livingston, Robert S. & Howard, F. T.
Partner: UNT Libraries Government Documents Department
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High Flux Isotope Reactor: a General Description

Description: Current status of the High Flux Isotope Reactor which is being planned for construction at Oak Ridge.
Date: March 15, 1960
Creator: Cole, T. E.
Partner: UNT Libraries Government Documents Department
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Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
Partner: UNT Libraries Government Documents Department
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Neutron Physics Division Annual Progress Report, September 1, 1958

Description: Report containing a series of reports from members of the Oak Ridge National Laboratory's Neutron Physics Division.
Date: February 15, 1958
Creator: Oak Ridge National Laboratory. Neutron Physics Division.
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Description: Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
Partner: UNT Libraries Government Documents Department
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Calculated Thermal Ionization And Enthalpy of Hydrogen, Nitrogen, And Argon At One Atmosphere Pressure In The 298-20, 000'K Temperature Range

Description: The degree of dissociation and ionization and the enthalpies of hydrogen and nitrogen, and the degree of ionization and the enthalpy of argon are calculated for one atmosphere pressure and temperatures up to 20,000'K. All three gases are more than 93% ionized at 20,000'K, and have enthalpies ranging from 553 kcals for argon to 1074 and 1225 kcals, respectively, for hydrogen and nitrogen.
Date: September 15, 1960
Creator: Bond, Walter Dayton
Partner: UNT Libraries Government Documents Department
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Natural Circulation Burn Out Heat Flux For The ORR

Description: Natural circulation flow rate is calculated for the ORR core. From this flow rate, the burn out heat flux is found to be between 22,000 and 35,000 Btu/ft2-hr. It is concluded that under present conditions a positive acting after heat removal system is necessary for 30 mw operation.
Date: February 15, 1960
Creator: Wett, J. F.
Partner: UNT Libraries Government Documents Department
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Oak Ridge National Laboratory Target Preparation Program

Description: In early 1961 a Target Fabrication Center was established at Oak Ridge National Laboratory to carry out the routine preparation of a wide variety of targets and to provide research and development support to the target program. Although most of the effort concerned enriched stable isotopes, both normal and radioactive materials are also handled. With the aid of rolling mills, resistance-heat and electron-bombardment vacuum evaporation, presses, and electroplating equipment, targets of elements … more
Date: January 15, 1963
Creator: Kobisk , E. H
Partner: UNT Libraries Government Documents Department
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