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Reactor Development Program Progress Report: March 1963

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: April 15, 1963
Creator: Adams, R. M. & Glassner, A.
Partner: UNT Libraries Government Documents Department

Tory II-C off-design performance

Description: This memorandum reports the performance of TORY II-C at off-design altitudes and Mach numbers. Inlet pressure recovery has been varied with Mach number, reasonable values for a real inlet having been chosen. Nozzle throat area and exit area have been fixed at the design values. Hence this study can be used, in conjunction with missile drag data, to construct a flight envelope.
Date: April 22, 1963
Creator: Moyer, J. H.
Partner: UNT Libraries Government Documents Department

Influence of a Sector Ground Screen on the Field of a Vertical Antenna

Description: Report show the field of a short vertical antenna on a homogeneous ground is modified by the presence of a metallic screen. The screen is taken in the form of a circular disk and a concentric sector. The modification of the field is expressed in the form of surface integrals over the disk and the sector. Extensive numerical results for these basic integrals are given and a number of applications are illustrated.
Date: April 15, 1963
Creator: Wait, James R. & Walters, Lillie C.
Partner: UNT Libraries Government Documents Department

Effect of Alloying Constituents on Aluminum Dissolution Rates

Description: In studies of the effect of alloying elements on the rate of dissolution of Al in mercury-catalyzed nitric acid, it was observed that Co, Ni, and Si present at concentrations of 1 to 2% have significant passivating effects. Fe was slightly catalytic. Passivation due to Si was partly overcome by contacting the passive alloy with active, high-purity Al. Increased catalyst concentration improved the rates when Ni and Si were present. Neither approach was effective when Cu was the passivating element. For application to nuclear fuel reprocessing, it is suggested that for minimum reprocessing costs the potentially passive Al alloys not be used in fuel elements or that, failing this, electrochemical activation techniques be applied at the processing plant. (auth)
Date: April 15, 1963
Creator: Fletcher, R. D.; Jacobson, M. E. & Beard, H. R.
Partner: UNT Libraries Government Documents Department

The Tensor Code

Description: The program, TENSOR, for the calculation of underground explosion phenomena and other time dependent problems involving the motion of elastic, plastic, fractured, and fluid materials is discussed. The method used in the code allows treatment of transient phenoraena in two space dimensions (cartesian or axial symmetry), and is particularly appropriate for problems involving compressible flow, large displacements, and free transitions of material between the elastic, cracked, plastic, and fluid states. The equations of motion are a straightforward generalization (to include a stress tensor) of conventional Lagrangian techniques for compressible flow and shock hydrodynamics problems. Methods for defining the stress system are discussed, and examples are included. (auth)
Date: April 1, 1963
Creator: Maenchen, G. & Sack, S.
Partner: UNT Libraries Government Documents Department

Army Reactors Program Annual Progress Report: 1962

Description: Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
Date: April 10, 1963
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department

Testing of Metal Volumetric Standards

Description: From Purpose: "The specifications and tolerances contained in this Monograph should be of assistance to purchasers of metal capacity standards. The information on methods of calibration and use of these measures should prove valuable to weights and measures officials and those persons in industry who are concerned with measurements of volumes of fluids."
Date: April 1, 1963
Creator: Hughes, J. C. & Keysar, B. C.
Partner: UNT Libraries Government Documents Department

Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1962 - March 1, 1963

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: April 1, 1963
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
Partner: UNT Libraries Government Documents Department

Interim Report: Faret Experimental Program

Description: From Introduction: "The Fast Reactor Test (FARET) program is part of the United States Fast Reactor Program directed toward the demonstration of breeder reactors essential to the long-range goal of utilizing fertile fuels. (1) With-in this program is the current thinking that the early construction and operation of two or three prototype nuclear power plants of the order of 250 Mw(e) will lead eventually to the construction of practical and economic full scale breeder reactors by the early 1980's. (2)"
Date: April 1963
Creator: Smaardyk, A.; Bump, T. R.; Handwerk, J. & Handwerk, J.
Partner: UNT Libraries Government Documents Department

Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)

Description: Report regarding "[t]he Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyro-metallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5 percent fissium and contains about 46 wt.% Uranium-235 . The blanket material consists of uranium in which plutonium is bred. Core and blanket subassemblies contained in transfer coffins are transferred between EBR-II and the Fuel Cycle Facility, which is in an adjacent building." (p. 13)
Date: April 1963
Creator: Hesson, J. C.; Feldman, M. J. & Burris, L.
Partner: UNT Libraries Government Documents Department

Distribution coefficient data and preliminary estimates of movement of radionuclides, Tatum salt dome, Lamar County, Mississippi. Technical letter: Dribble 31

Description: Estimates are made relating radionuclide movement to ground water velocity as part of the safety program for a proposed experiment to detonate nuclear devices within the Tatum salt dome. The estimates are based on distribution coefficients obtained from laboratory studies. Core samples obtained from hydrologic test well HT-3, Tatum salt dome, Lamar County, Mississippi, were equilibrated with radionuclides in solutions simulating aquifer waters found in the area. The combinations of Cenozoic sand and silty clay, and quality of water of the area were studied and summarized. The distribution coefficients obtained for different radionuclides were tested and indicate retardation factors from 1.3 to 857 for the travel time of these radionuclides when compared to the travel time of water in the aquifer system. Laboratory results indicate that migration of any radioisotope inadvertently introduced to the aquifers in the vicinity of the dome as a result of proposed nuclear test explosions would be extremely slow. Revised estimates of the rate of dissolved radioisotope movement will be made on the basis of further laboratory studies utilizing chromatographic adsorption columns of 0.5 to 4.0 feet in length.
Date: April 10, 1963
Creator: Beetem, W.A. & Janzer, V.J.
Partner: UNT Libraries Government Documents Department

HIGH-TEMPERATURE LIQUID-METAL TECHNOLOGY REVIEW. A Bimonthly Technical Progress Review. Volume 1, Number 2

Description: Metals ---technology of high-temperature liquid, review; Systems for Nuclear Auxiliary Power (SNAP-2) ---coolant boiling research for; Nuclear Power Plants ---development research on thermionic, Los Alamos Molten Plutonium Reactor Experiments ---fuel element analysis; Heat Transfer Systems ---conference on liquid metal; Bearings --coating for liquid metal, performance of; Systems for Nuclear Auxiliary Power (SNAP-8) ---component development; Sodium---heat transfer research on; Mercury --heat transfer research on; Potassium ---heat transfer research on; Nitrogen Systems ---Hg --N, flow characteristics for two-phase; Mercury Systems ---Hg --N, flow characteristics for two-phase; Nuclear Power Plants ---heat transfer rejection by space, research on; Alkali Metals ---heat transfer research on; Turbines ---development of twostage potassium; Bearings --- development of liquid-metal lubricated; Niobium Alloys ---properties for alkali metal containment, research on; Rubidium ---thermophysical properties of; Los Alamos Molten Plutonium Reactor Experiments ---design of LAMPRE-1. (D.C.W.)
Date: April 1, 1963
Creator: Dwyer, O. E.
Partner: UNT Libraries Government Documents Department

A Mathematical Model For an Associative Memory

Description: Abstract: A mathematical model for an associative memory is proposed which uses associative addressing and distributed storage.
Date: April 1963
Creator: Simmons, G. J.
Partner: UNT Libraries Government Documents Department

Data for Elementary-Particle Physics

Description: These data are provided: Masses and .Mean Lives of Elementary Particles; Atomic and Nuclear Properties of Materials; Particle Scattering; Atomic and Nuclear Constants; Particle Decay and Reaction Dynamics; Tentative Data on Strongly lnteracting Particles and Resonances; and Clebsch-Gordan Coefficients and Spherical Harmonics.
Date: April 30, 1963
Creator: Rosenfeld, A. H. & Barkas, W. H.
Partner: UNT Libraries Government Documents Department