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Operating Procedure for the Bulk Shielding Reactor, Fourth Edition

Description: Report issued by the Oak Ridge National Laboratory discussing the 4th revision to the operating procedures used with the bulk shielding reactor. Standard procedures, emergency procedures, and authorized personnel for the bulk shielding reactor are presented. This report includes tables, and illustrations.
Date: January 2, 1959
Creator: Henry, K. M. & Maienschein, F. C.
Partner: UNT Libraries Government Documents Department
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Design Bases for ICPP Waste Calcination Facility

Description: Report regarding a waste calcination unit that "will convert the fission product-containing aluminum nitrate solutions" "to granular alumina and fission product oxides" (p. 5).
Date: January 16, 1959
Creator: MacQueen, D. K. & Stevens, J. I.
Partner: UNT Libraries Government Documents Department
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Informal progress report of the explosives group. Quarterly progress report, September--November 1958

Description: The relatively high heats of combustion of CHN compounds containing multiple bonds has prompted an investigation of the possible use of these compounds as explosives components. Three possible systems are being considered for testing in the small scale plate push apparatus: acrylonitrile-tetranitromethane, propiolonitrile-tetranitromethane and dicyanoacetylene-tetranitromethane. Samples of propiolamide and acetylene dicarboxamide, intermediates in the synthesis of propiolonitrile and dicyanoace… more
Date: January 7, 1959
Creator: Kury, J.
Partner: UNT Libraries Government Documents Department
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SNAP II

Description: slide presentation
Date: January 15, 1959
Partner: UNT Libraries Government Documents Department
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Experimental Pressure Distributions and Force Coefficients on Block Forms for Varying Mach Number, Reynolds Number, and Yaw Angle

Description: Abstact: "Wind tunnel tests were performed to determine pressure distributions and normal force coefficients on three block forms on mounting planes. The dimension ratios of the blocks were 1:1:1, 1:1:2, and 1:1:4. Results are given for variation in Mach number from 0.066 to 0.8, in Reynolds number from 0.28 x 10(exp 6) to 4 x 10(exp 6), and in yaw angle from 0 to 90 degrees. Results show a Reynolds number independence over the range examined. Windward face force coefficients for a given block … more
Date: January 1959
Creator: Hankins, Dorris M.
Partner: UNT Libraries Government Documents Department
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Furnace Brazing of Zircaloy

Description: The furnace brazing of Zircaloy or Zircaloy-clad nuclear reactor components was investigated. The strength and corrosion resistance of brazements were determined and techniques were developed for preplacing the brazing alloy to prevent contamination and to maintain dimensional stability during brazing. Brazements of high strength and adequate dimensional accuracy were produced, but the brazing cycles impaired the corrosion resistance of Zircaloy in high-temperature steam and water. (auth)
Date: January 1, 1959
Creator: Slaughter, E. R.
Partner: UNT Libraries Government Documents Department
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A MODEL OF BUBBLE GROWTH IN THE KEWB REACTOR

Description: Short-period transients (less than 15 msec) in the KEWB reactor are apparently controlled primarily by void production resulting from gas evolution in the core. A growth mechanism probably prevails during the short-period excursions which differs from that which occurs at longer periods. Experimental data were examined which showed that the energy transferred to the average bubble is an order of magnitude less than that required to cause bubble growth. It is believed, however, that the validity… more
Date: January 1, 1959
Creator: Gamble, D.P.
Partner: UNT Libraries Government Documents Department
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ROUGHENING OF HEAT TRANSFER SURFACES AS A METHOD OF INCREASING HEAT FLUX AT BURNOUT

Description: The bunnout heat flux and friction factors for rough surfaces were measured for vertical tubes cooled by downward flow of water. An increase in the burnout heat flux of as much as l00% over a smooth surface was obtained at the same coolant velocity, temperature, and pressure. A nat gain of as much as 80% in heat flux at burnout is possible if the coolant channel is widened to permit the same flow at the same pumping requirements as a smooth surface. The results of 50 experiments were correlated… more
Date: January 1, 1959
Creator: Durant, W. S. & Mirshak, S.
Partner: UNT Libraries Government Documents Department
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REACTOR FUEL WASTE DISPOSAL PROJECT DEVELOPMENT OF DESIGN PRINCIPLE FOR DISPOSAL OF REACTOR FUEL WASTE INTO UNDERGROUND SALT CAVITIES

Description: Waste disposal in underground salt cavities is considered. Theoretical Investigations for spherical and cylindrical cavities included analysis of elastic stress, thermal stress, and stress redistribution due to the development of a plastic zone around the cavity. The problems of temperature distribution and accompanying thermal stress, due to heat emission from the waste, were also studied. The reduction of the cavity volume, the development of the plastic zone, and the resulting stress redistr… more
Date: January 1, 1959
Creator: Serata, S. & Gloyna, E.F.
Partner: UNT Libraries Government Documents Department
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Neutron-Flux Measurements in a Concentric-Cylinder Fuel Element

Description: Neutron-flux measurements in a concentric-cylinder fuel element were made in a gas-cooled in-pile loop operated adjacent to the core of the BRR. The fuel element comprised four concentric fuel cylinders. Each fuel annulus (outside diameters- 1.248 1.018, 0.810 and 0.590 in.) consisted of a 0.031-in.- thick core of UO/sub 2/ dispersed in type 347 stainless steel and clad on each side with 0.007 in. of typee 318 stainless steel. The element was 24 in. long and the total uranium-235 content was ap… more
Date: January 29, 1959
Creator: Anno, J. N.; Fairand, B. P. & Chastain, J. W., Jr.
Partner: UNT Libraries Government Documents Department
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Some Effects of Radiation on Solvent Extraction Processes

Description: The yield of total acid, G/sub acid/, in the radiolysis of tributyl phosphate-Amsco 125-82 solutions is 2.7 times the electron fraction of TBP, or approximately 2.7 times the weight fraction of TBP, per 100 ev of energy absorbed by the solution. Dibutyl phosphoric acid, DBPA, constitutes about 85% of the acid. Radiolysis of TBP also results in the conversion of abcut 0.9 molecules of TBP to a polymer per 100 ev of energy absorbed. Uranium extraction-stripping tests with an 8 stage spinner colum… more
Date: January 26, 1959
Creator: Davis, Wallace, Jr. & Wagner, Robert M.
Partner: UNT Libraries Government Documents Department
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A Table of Emission Lines in the Vacuum Ultraviolet for All Elements (6 Angstroms to 2000 Angstroms)

Description: All the published atomic emission lines contained in the literature up to January 1959, are presented. Each line of data contains the vacuum wavelength in Angstroms, the element and spectroscopic notation for ionization the intensity, and reference numbers which refer to the list of references at the end of the report. Lists of intense lines arranged by ions, lines arranged by element, and binding lists are included. The intensities given in the tables are those published for spark sources. (W.… more
Date: January 1, 1959
Creator: Kelly, R.L.
Partner: UNT Libraries Government Documents Department
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FIELD STUDY OF THE AgPO$sub 3$ GLASS PERSONNEL DOSIMETER (U.S. NAVY DT-60)

Description: >The U. S. Navy DT-60 dosimeter was evaluated under field type conditions as to its reproducibility and accuracy of gamma x-ray, thermal and fast neutron and mixed radiation responses. Gamma and x-ray responses from 25 to 600 rads at energies in oxcess of 200 kev were found to be accurate within 20% in 92% of 160 dosimeters examined. Because the DT-60 was found to have no detectable fast neutron response, effort was directed toward exaggerating the thermal neutron response to approximate the to… more
Date: January 1, 1959
Creator: Ballinger, E.R. & Harris, P.S.
Partner: UNT Libraries Government Documents Department
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FINAL REPORT ON MISCIBILITY GAPS IN Nb-U AND Nb-U-Zr SYSTEMS

Description: The miscibility gap in the U-Nb system has been established using metallographic and x-ray techniques. The monotectoid temperature is placed at 640 deg plus or minus 2 deg C and the composition limits at that temperature are 65 to 70 at.% Nb and 17.5 plus or minus 1 at.% Hb. The 700, 650, and 600 deg C isothermal sections of the U-Nb- Zr system have also been investigated. Each of the miscibility gaps present in the limiting binary sections was found to be closed by additions of the third eleme… more
Date: January 1, 1959
Partner: UNT Libraries Government Documents Department
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Core Characteristics of Four Army Package Power Reactors

Description: A brief discussion of the core charteristics of four uranium fuel, pressurized-water type: Army Package Power Reactors, the SM-1, SM-1A, PM-2A, and SW-2, is presented. The characteristics discussed are cell geometry, fuel plates, core geometry, flux distributions, core loading, core burnout, and control reds. Tables and illustrations are included. (auth)
Date: January 1, 1959
Creator: Gallagher, J. G.; Leibson, M. J. & Byrne, B. J.
Partner: UNT Libraries Government Documents Department
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Canning Graphite for Gas-Cooled Reactors

Description: A preliminary investigation was made of techniques and materials for canning graphite to protect it for use at high temperatures in a nitrogen--oxygen atmosphere. Fabrication techniques for cladding bare and copper--plated graphite cores either in Type 316 stainless steel or Inconel X were developed. Specimens of the various combinations of core and cladding materials were subjected to simulatedservice conditions and evaluated. In all cases the Type 316 stainless steel-clad specimens failed by … more
Date: January 1, 1959
Creator: Paprocki, S. J.; Carlson, R. J. & Bonnell, P. H.
Partner: UNT Libraries Government Documents Department
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Maximum Accelerators Caused by Underground Nuclear Explosions in the Oak Spring Formation in Area 12 of the Nevada Test Site at Distances of 5 to 300 Kilometers: a Preliminary Summary

Description: From introduction: The results presented in this preliminary report are principally concerned with the ground motion caused by seven underground nuclear explosions (table 1) in the bedded tuff of the Oak Spring formation in Area 12. Ground motions were recorded at stations as close as 5 kilometers and as far as 300 kilometers from the explosions (fig 1 and table 2). The results for the Bianca and especially the Evans explosion are meager because the first was accompanied by a Test Site-wide moz… more
Date: January 1959
Creator: Stewart, S. W.; Roller, J. C. & Diment, William H.
Partner: UNT Libraries Government Documents Department
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A Simple Calibration and Checking Facility for Fast and Slow Neutron Detectors

Description: From introduction: The principal work described below is the development and tests of a slow neutron flux generator based on a generator developed at the University of California (UCRL 8359, W. Patterson, Roger Wallace, "A Method of Calibrating Slow Neutron Detectors"). It is shown that a tolerance flux density of slow neutrons results within a cubical cavity 15 inches on an edge with 4-inch-thick walls of water or paraffin wax when a plutonium-beryllium source emitting about 7 million neutrons… more
Date: January 28, 1959
Creator: Redmond, A. H.
Partner: UNT Libraries Government Documents Department
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ORBIT DYNAMICS IN THE SPIRAL-RIDGED CYCLOTRON

Description: Formulas are derived for the equilibrium orbit, isochronous condition, vertical and horizontal betatron frequencies, and for the effects of the 3/3 radial resonance in a three-fold geometry. The magnetic field is represented by a Fourier series in azimuth with amplitudes expanded in a Taylor series about the reference radius. The form is such that the various parameters may be deduced from an arbitrary set of field measurements in the median plane and the results obtained by direct substitution… more
Date: January 12, 1959
Creator: Smith, Lloyd & Garren, Alper A.
Partner: UNT Libraries Government Documents Department
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REQUIREMENTS FOR RAW MATERIALS IN AN EXPANDING NUCLEAR POWER ECONOMY

Description: The need for breeding does not appear to be highly cost for a moderately optimistic expanding nuclear power economy between 1960 and 2000. Since the expansion rate of the US nuclear economy is assumed to be high at least 2/3 of the U-235 recovered from natural uranium is used to supply reactor inventory. It is the remaining 1/3 of the available U-235 that can be saved by breeder breeders or a breeder and converter are the doubling time and a parameter expressing the total fissile inventory per … more
Date: January 20, 1959
Creator: Arnold, E.D. & Ullmann, J.W.
Partner: UNT Libraries Government Documents Department
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Radiation: A Tool for Industry. A Survey of Current Technology

Description: This one-year survey of industrial applications of ionizing radiation is based on interviews with workers in the field and on analysis of selected literature. ionizing radiation at kilowatt power levels from electron accelerators and from radionuclides is finding a few special applications, notably sterilization and be in various stages of process development and tcsting. These are concentrated heavily in the plastics field, though examples are found in petrochemical synthesis, product steriliz… more
Date: January 1, 1959
Partner: UNT Libraries Government Documents Department
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