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Effects of Insulin of Hepatic Glucose Metabolism and Glucose Utilization by Tissues

Description: The mechanism whereby insulin lowers the blood glucose concentration is currently under extensive investigation. Despite the general agreement that the addition of insulin increases glucose uptake by various isolated tissues, the question has been raised whether administered insulin produces its blood sugar lowering effect in vivo primarily in increasing glucose uptake. Furthermore, it has been suggested that physiologically-released insulin may not exert the same effects as are produced by administered insulin. Attention has also been focused on whether insulin (exogenous or endogenous) exerts its action mainly or entirely on the liver and to what extent insulin influences glucose uptake and glucose production by the liver. The studies to be reported are a continuation of earlier work and are concerned with the effects of insulin, both exogenous and endogenous, on glucose utilization by the tissues and glucose production by the liver under various dietary condition in the unanethetized, intact dog, using C¹⁴ glucose.
Date: [..1961]
Creator: de Bodo, R. C.; Steele, R.; Altszuler, N.; Dunn, A. & Bishop, J. S.
Partner: UNT Libraries Government Documents Department
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Elastic Scattering of 31-Mev He$sup 3$ Ions From Several Elements

Description: The absolute differential cross sections for elastic scattering of 31- Mev He/sup 3/ ions on Be, Al, Cu, Sn/sup (nat)/, Sn/sup 120/ and Bi were measured in the angular range of approximately 10 to 120 deg in the center-of-mass system. Thin selfsupporting foil targets were chosen to span the parameter A/sup 1/3/, where A is the target mass number. The first excited states of the isotopes of these elements had sufficient energy separation from the ground state to enable elastic scattering to be resolved from inelastic scattering. The detection system, consisting of CsI(Tl) scintillation crystals, was capable of 3% pulse- height resolution and 1 degree angular resolution. Characteristically, the light- element angular distributions show strong diffraction effects. The differential cross section divided by the Rutherford cross section decreases exponentially at large angles for the heavy elements, and the differential cross sections break away from Rutherford behavior at angles which increase almost linearly with increase of atomic number of the target nucleus. A comparison of the results for natural Sn, and Sn enriched to 85% in Sn/sup 120/, indicated that within the experimental uncertainties over the measured angular interval, there were no pronounced isotopic effects. The data are presented both in tabular and graphical form to allow detailed comparison with theory. (auth)
Date: December 31, 1961
Creator: Igo, G.; Vidal, J. G. & Markowitz, S. S.
Partner: UNT Libraries Government Documents Department
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The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System

Description: Abstract: Electrical resistance measurements and metallography were employed in a study of the kinetics of the gamma to gamma prime transformation in the uranium-molybdenum system at 16 wt% molybdenum.
Date: December 31, 1961
Creator: Kramer, D. & Rhodes, C. G.
Partner: UNT Libraries Government Documents Department
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The Influence of Nuclear Radiation on the Corrosion of Metals. Paper 3 of Fourth Radiation Effects Symposium, September 15-16, 1959, Cincinnati, Ohio. General Session Papers

Description: The effect of radiation on the corrosion of metals is reviewed relative to corrosion-resistant characteristics of metals; effects of radiation on the medium and subsequent effect of corrosion of the metal; and the effect of service loads on the corrosion of metals in a nuclear environment. 31 references. (C.J.G.)
Date: December 31, 1961
Creator: Younger, C. L.
Partner: UNT Libraries Government Documents Department
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Radioactive contamination in liquid wastes discharged to ground at separations facilities through December 1961

Description: This document summarizes the amounts of radioactive contamination discharged to ground from separations facilities through December 1961. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of July through December 1961. Previous publications of this series are listed in the bibliography and may be referred to for specific information on measurements and radioactivity totals prior to December 1961.
Date: December 31, 1961
Creator: Backman, G. E.
Partner: UNT Libraries Government Documents Department
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Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1961 - December 1, 1961

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: December 30, 1961
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
Partner: UNT Libraries Government Documents Department
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Mound Laboratory Progress Report for December 1960

Description: Activities are reported in a program to investigate formulations and procedures which may lead to superior plastics and adhesives. In other work, processes for separating and purifying radioelements are being developed and supply sources are being evaluated. Research was initiated to determine the density, viscosity, thermal capacity, and thermal conductivity of Pu and Pu alloys for use in fast breeder reactors. (J.R.D.)
Date: December 30, 1961
Partner: UNT Libraries Government Documents Department
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ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART I. ZIRCONIUM IN HCl- METHANOL

Description: The electrolytic dissolution of zirconium in HCl-methanol was studied as a function of potential, solution composition, and temperature. The dissolution is characterized by two regions. At high potentials the zirconium is electropolished and complete dissolution is achieved. At low potentials the current is an exponential function of the potential (Tafel behavior). In this region a small amount of finely divided alpha -zirconium which is insoluble in HCl-methanol separates from the bulk metal. The energy of activation for the corrosion reaction (0.0 volt) is 16.5 kcal/mole; in the electropolishing region (1.0 volt) the activation energy is 7.7 kcal/mole. A broad solvent capability for metallic reactor fuels is offered by the HCl-methanol medium since, in addition to zirconium, stainless steel is also dissolved electrolytically while uranium and aluminum dissolve chemically. Other process implications are discussed. (auth)
Date: December 29, 1961
Creator: Aylward, J. R.; Whitener, E. M. & Hahn, H. T.
Partner: UNT Libraries Government Documents Department
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Electrolytic Oxidation of Zirconium in Nitrate Solutions

Description: Zirconiurn alloys used in the fabrication of nuclear fuel elements can be disintegrated and converted to insoluble oxides by electrolytic treatment in concentrated nitrate solutions. This reaction shows promise as a technique for reprocessing nuclear fuels clad with Zircaloy-2. For a particular applied voltage, nitric acid achieves the highest rate of attack, but the reaction can be carried out at rates of 2 mg/(cm/sup 2/)(min) or greater in either 7.5M sodium nitrate or 2.3M aluminum nitrate. A reaction rate of 7 mg/(cm/sup 2/) (min) can be easily attained in either 8M nitric acid or 7.5M sodium nitrate. The rate of reaction is a function of the temperature and tho applied voltage. An as-yet unsolved problem is the carry--down of uranium with the insoluble zirconium oxide product. (auth)
Date: December 29, 1961
Creator: Bomar, M. R.
Partner: UNT Libraries Government Documents Department
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Tables of Spectral-Line Intensities: Part 1, Arranged by Elements

Description: Abstract: "These data are presented by element in part I, and all 39,000 observed lines are given in order of wavelength in Part II." From Introduction: "In the beginning, most intensity data were reported on an arbitrary scale of 10 steps, weak lines being assigned an intensity of 1, and the strongest line intensity 10."
Date: December 29, 1961
Creator: Meggers, William F.; Corliss, Charles H. & Scribner, Bourdon F.
Partner: UNT Libraries Government Documents Department
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Core Design Study for a 500MWe Fast Oxide Reactor

Description: A 500 MWe sodium-cooled, PuO2-UO2 fuel, fast spectrum reactor design is presented, which is calculated to have a fuel cycle cost in the civinity of 1 mill/ekw hr, and to have important safety features due to an appreciably negative Doppler effect.
Date: December 28, 1961
Creator: Horst, K. M.; Hutchins, B. A.; Leitz, F. J. & Wolfe, B.
Partner: UNT Libraries Government Documents Department
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Failure Analysis of Dispersion Fuel Elements Based on Matrix Cracking

Description: A mathematical model has been developed for estimati the burnup at which mechanical failure occurs in dispersion fuel elements. It is postulated that failure at low temperature, < 900 deg F, occurs as a result of brittle fracture of an elastic matrix when the intensity of the stress locally reaches the ultimate strength of the material. The contributions of fission gas pressure and thermal stress are incorporated in the stress analysis. Because of the complexity of the stress distribution and the failure process, it was necessary to make stringent assumptions in order to have a workable model. Within the framework of the postulates, burnups to failure are predicted for several values of certain important parameters and compared with burnups to failure obtained from a plastic yield model for failure developed by previous investigation. The two models give good agreement for the special cases considered. Of the parameters examined, relative density of the fuel particles has the greatest influence on predictions of allowable burnup. The thermal stress and volume fraction of fuel play minor roles. (auth)
Date: December 28, 1961
Creator: Beck, S. D.
Partner: UNT Libraries Government Documents Department
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REMOTELY CONTROLLED SHEARING OF PIPE AND STRUCTURAL MEMBERS

Description: A shearing tool was developed for remotely controlled severing of pipes or structural members. The shear is rotated about its axis in a wrist motion by the pumped hydraulic fluid that also powers the shear blade. It can be used in a stationary mounting or suspended from a crane. A C-shaped support for the shear was designed to pass through a small top opening of a shielded cell. The controls for manipulating the shear pass through or along the Cframe. The shear jaw opens to 5 in. in height and 7 in. in width, and the total weight of the tool is only 575 lb. It was used to cut metal sections 4 3/4 in. thick and 4-in. sched.-40 stainless steel pipe. (auth)
Date: December 28, 1961
Creator: Abbatiello, A. A.
Partner: UNT Libraries Government Documents Department
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RADIOACTIVE FILTER BANK FIRE DETECTION SYSTEMS

Description: The detection of radioactive air filter fires is discussed. Criteria requirements for a suitable fire detection system were established. The applicability of aircraft-type fire detection systems for this use was evaluated. The operation of a discrete eutectic salt type continuous fire detection tubing system is outlined. (M.C.G.)
Date: December 27, 1961
Creator: Walker, R.W.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, May 1961

Description: The experimental results on the oxidation of H from a He stream with CuO pellets were very close to the predicted behavior based on the mathematical model. Experimental measurements of uranyl sulfate loading rates on chloride equilibrated resin showed little variation with solution concentrations. A tentative flowsbeet was proposed for cost analysis of processing a Pebble Bed Reactor. A U-Zr plate was dissolved in nitrate-free Zirflex solution. An authentic TRIGA prototype was processed in engineering-scale equipment. Three 4- stage leacher model dissolution runs were made, two of which used 8 M HNO/sub 3/ and one used 4 M HNO/sub 3/. Flooding rates and holdup data were obtained for sieve plate pulse columns under 5% TBP - l.8 Mi Al(NO/sub 3/)/sub 3/ flowsheet conditions. A Purex waste calcination run (R-37) was made using sodium anid imagnesium to reduce sulfate volatility. (auth)
Date: December 26, 1961
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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MAGNETIC MEASUREMENTS OF AGS EXPERIMENTAL MAGNETS

Description: BS>The approach taken in measurements on the AGS experimental magnets is discussed, and results of various measurements are examined. Application of information to calibration of beam lenses is also mentioned. Graphs of several magnet properties are included. (D.C.W.)
Date: December 26, 1961
Creator: Danby, G.T.
Partner: UNT Libraries Government Documents Department
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EXPERIMENTAL ATTEMPTS TO STABILIZE A CUBIC FORM OF BeO

Description: Binary mixtures of BeO with the oxides Al/sub 2/O/sub 3/, CaO, Li/sub 2/ O, MgO, Sc/sub 2/O/sub 3/, TiO/sub 2/, Y/sub 2/O/sub 3/, and ZrO/sub 2/ were fired to temperatures in excess of 2050 deg C in an attempt to produce a stabilized cubic crystalline modification of BeO. No evidence was observed in microscopic and x-ray diffraction analyses of the cooled specimens that a cubic form of BeO had formed in the experiment. (auth)
Date: December 22, 1961
Creator: Thoma, R.E.; Friedman, H.A. & McVay, T.N.
Partner: UNT Libraries Government Documents Department
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MARITIME GAS-COOLED REACTOR PROGRAM. A REVIEW OF THE MARITIME GAS-COOLED REACTOR PROGRAM

Description: Presented at the Eleventh Professional Divisions Conference of the San Francisco Section of the American Society of Mechanical Engineers, Noveraber l6, l96l. The MGCR program and its objectives are discussed. The basic MGCR plant is described. The design of the Experimental Beryllium Oxide Reactor is also described. (M.C.G.)
Date: December 22, 1961
Creator: Trickett, K.A.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: November 1961

Description: This report for November 1961, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; and special separation processing and auxiliaries operation.
Date: December 21, 1961
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF RING-JOINT FLANGES FOR USE IN THE HRE-2

Description: Ring-joint flanges were studied in thermal-cycle tests as part of the development work associated with Homogeneous Reactor Experiment No. 2 (HRE-2). The purpose of this study was to provide criteria for design, installation, and operation of joints that would remain leaktight under reactor operating temperatures and pressures. Joints ranging from 1/2 in., l500 lb to 4 in., 2500 lb and with various initial bolt loadings were cycled between room temperature and 636 deg F. It was demonstrated that when joints were made up to HRE-2 standards and specifications, leak rates of less than 0.25 x 10/sup -3/ g of water per day per inch of gasket pitch diameter could be routinely- attained. Undamaged gaskets could be reinstalled or new gaskets used with equal probability of achieving acceptable leak rates. The system installed in HRE-2 was provided with a high-pressure buffer system to ensure that the small amount of leakage to the cell would be nonradioactive. (auth)
Date: December 21, 1961
Creator: Robinson, J. N.; Lundin, M. I. & Spiewak, I.
Partner: UNT Libraries Government Documents Department
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Large-Scale Slurry-Circulation System, 300-SM

Description: Design philosophy, status of component development, operational procedures, and limitations of each section of the Oak Ridge large-scale, high-temperature, thoria slurry facility.
Date: December 21, 1961
Creator: Parsly, L. F., Jr.; Falkenberry, H. L.; Harley, P. H.; Miller, I. M. & Kenyon, V. L.
Partner: UNT Libraries Government Documents Department
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