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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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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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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 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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Some Experiments Relating Ion Diffusion in a Plasma to the Neutral Gas Density in the Presence of a Magnetic Field

Description: In some recent experiments the ion density in a plasma was measured as a function of radial distance from a d-c arc source of ions for the magnetic field intensities from 2500 to 14000 oersted. The diffusion coefficient appeared to very inversely as the square of the magnetic field strength, D~1/H2. The absolute value of D was shown to be approximately that which would be predicted by the collision diffusion theory when account is taken of the shorting effect of the end walls. The purpose of th… more
Date: June 15, 1956
Creator: Reidigh, Rodger V.
Partner: UNT Libraries Government Documents Department
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Examination of 6" Diameter "O" Ring from HRT Mockup. Metallography Report (Y-12) No. 39

Description: A six-inch diameter "O" ring from the HRT Mockup was examined metallographically after 2452 hours exposure to uranyl sulfate solution at 300C. surface defects, except for cold work defects were found only in areas exposed to uranyl sulfates. Defects found were pits, transgranular cracks, surface cracks, and grain attacks.
Date: January 15, 1957
Creator: Kegley, T. M., Jr.
Partner: UNT Libraries Government Documents Department
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Effects of Heat Treatment on Microstructure and Fabricability of 48 wt % Uranium - 52 wt % Aluminum Alloys

Description: It has been reported in the literature that prolonged soaking of 16 wt & uranium-aluminum alloys at elevated temperatures induces a microstructural changed termed "conglobulation". this process is essentially a spheroidization of the UAl4 eutectic. Conclusions of the tests: (1) Extended soaking of 48 wt $ uranium-aluminum alloy billets at 600 C does not improve their hot-rolling characteristics. (2) Soaking periods of 50 hours and greater reduce the tensile and yield strengths of these alloys.… more
Date: March 15, 1957
Creator: Thurber, William C.
Partner: UNT Libraries Government Documents Department
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The Volatilization of Fission Products by Melting of Reactor Fuel Plates

Description: Experiments in the controlled melting of irradiated fuel specimens, particularly of the APPR, STR, and MTR types have confirmed that prolonged heating in air at temperatures in excess of the melting point results in the release of a large portion of the radioactivity. On the other hand, a moderate amount of heating in air or steam sufficient only to melt a specimen results mainly in the partial volatilization of the rare gases; the halogens, iodine and bromine; and the alkali metals, cesium and… more
Date: July 15, 1957
Creator: Parker, Geogre W. & Creek, George E.
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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Disassembly and Postoperative Examination of the Aircraft Reactor Experiment

Description: The Aircraft Reactor Experiment (ARE)was successfully concluded in November of 1954, and a detailed report of the operation was published the following year. At that time it was thought that an extensive examination of the reactor and system components after disassembly was warranted. It was realized, of course, that the level of radioactivity of the components would necessitate extensive delays in the examinations. Since examination of a few critical ARE samples showed nothing unexpected, much… more
Date: April 15, 1958
Creator: Cottrell, W. B.; Crabtree, T. E.; Davis, A. L. & Piper, W. G.
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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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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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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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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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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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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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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Description of a Proposed Program: Dynamic Analysis of Radiochemical Plant Components

Description: A study is proposed to analyze the solvent extraction operation in order to produce a method of calculating steady state contactor performance for optimizing new flow sheets, and to describe the transient effects in the operation in order to better understand the limitations of the steady state model, to establish quantitative criteria for control, and to provide models for future application to computer controlled plants.
Date: December 15, 1959
Creator: Whatley, M. E. (Marvin E.), 1926-
Partner: UNT Libraries Government Documents Department
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Problem Statement - Treatment of Declad Wastes for Disposal

Description: It is proposed that decladding wastes be converted to dry solid "packages" suitable for ultimate storage in a dry environment. Low temperature solidification of Sulfex and Zirflex decladding wastes by addition of lime, plaster of paris, portland cement, drying agents, etc. seems feasible. A similar treatment of Darex decladding wastes probably should be preceded by chloride removal and nitrate destruction. Calcination may be a preferable alternative for Darex wastes.
Date: December 15, 1959
Creator: Roberts, J. T. & Tomlin, W. E.
Partner: UNT Libraries Government Documents Department
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Status Report of the Soluble Poison Shim Control for the HFIR

Description: A number of chemicals have been investigated for their possible use as a soluble poison for the HFIR shim control. A preliminary flowchart was drawn and some heat generation calculations in Zircaloy-2 and boric acid poison solution were made.
Date: December 15, 1959
Creator: McLain, H. I.
Partner: UNT Libraries Government Documents Department
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Nuclear Characteristics of BeO-Moderated Cores vs Graphite-Moderated Cores

Description: Multigroup calculations were performed to compare BeO-moderated cores, using various void fractions and core diameters. The core leakages and conversion ratios which were calculated are presented in a series of curves.
Date: January 15, 1960
Creator: Carlsmith, R. S.
Partner: UNT Libraries Government Documents Department
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