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Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading

Description: A recommended SM-1A Core I loading chart was derived from available, metallurgically acceptable elements at the SM-1A and SM-1 sites. The derivation was based on local thermal and hydraulic considerations of minimum elementto- element coolant channel clearances. These clearances were determined from field inspection measurements of outer fuel plate spacing, as modified by analytical calculations of plate ripple growth during exposure to reactor operating thermal stresses. (auth)
Date: January 10, 1962
Creator: Brondel, J. O.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, June 1961

Description: An interfacial viseometer was built for use in an interfacial phenomena study. Installation of a 6-in.-ID foam separation column system was completed. The dispersiondrying-sintering characteristics of six low-nitrate batches of thoria sol material were studied. The average effective porosity of the CuO pellets used for reactor helium purification was determined to be 0.0545 for H/ sub 2/ transport and 0.0526 for CO transport. In continuous Zirflex dissolution studies, no H/sub 2/O/sub 2/ decomp… more
Date: January 23, 1962
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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Determination of Heavy Water Purity by Infrared Absorption

Description: The practical application of heavy water purity determination by infrared absorption spectroscopy using standard laboratory equipment was demonstrated in connection with the operation of heavy water-moderated Special Power Excursion Reactor Test (SPERT II) Facillty at the NRTS. (auth)
Date: January 16, 1962
Creator: Abernathey, R. M. & Morgan, T. D.
Partner: UNT Libraries Government Documents Department
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THE THEORY AND MEASUREMENT OF CRITICALITY

Description: ABS>The measurable properties of a critical assembly (e.g.. fission, capture, and leakage rates; neutron-per-fission ratios; bare/Cd-covered reaction rate of-atios; danger eoefficients; etc.), whose judicious use completely defines tbcneutron economy in the assembly, are discussed. Require ments regarding the internal consisteney of these of:deasured quantities are reviewed. lt is concluded that theoretical analysis of the assembly must both reproduce the gross experimental results and reflect … more
Date: January 1, 1962
Creator: Kelber, C.N.
Partner: UNT Libraries Government Documents Department
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Physics Division Summary Report

Description: The use and operation of the 4.5-Mev Van de Graaff generator ts descrtbed. Sputtering experiments were conducted by bombarding single crystals of electrolytic copper wtth deuterons with energies of 0.8 to 2.5 Mev. The experimental results are discussed on the basis of existing sputtering theories. The kinetic-energy distribution and Boltzmann "temperatures" of most of the fragments of cyanogen under electron impact were determined. A lower limit of 0.05 ev for this temperature'' was also determ… more
Date: January 1, 1962
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium. Quarterly Report No. 1, September 15, 1961 to December 14, 1961

Description: A research program to determine the extent to which Zr and Zircaloy-2 exhibits delayed fnilure (static fatigue) as caused by absorbed H/sub 2/ and applied stress is outlined. Dynamic tensile tests were carried out on Zr and Zircaloy-2 without and wlth 200 ppm H/sub 2/. Preliminary results of a delayed failure investigation suggest that Zr containing 200 ppm H/sub 2/ is relatively insensitive to delayed ailure at room temperature up to 900 hr. (D.L.C.)
Date: January 1, 1962
Partner: UNT Libraries Government Documents Department
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Effects of Temperature on Mechanical Properties of Normal Uranium Dingot

Description: Fatigue properties of normal uranium dingot for rotating beam specimens between 150 and 600 deg C are shown as S-N diagrams and are also given by an empirical equation of the form S = bN/sub m/, where S is the stress, N the number of cycIes, and b and m temperature dependent parameters. Tensile properties for temperatures ranging from 30 to 700 deg C are presented in tabular form and as stress-strain diagrams. All of the properties were found to decrease in value with increasing temperature exc… more
Date: January 1, 1962
Creator: Pederson, K. & Murphy, G.
Partner: UNT Libraries Government Documents Department
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Critical Studies of a Fast Reactor Core Containing Depleted Uranium and Sodium as Diluents. (ZPR-III Assembly 36)

Description: Critical studies were performed with a metallic, fast reactor core designed to snvestigate the effects of replacing highly absorbing U/sup 238/ diluent with high-scattering, lowabsorbing sodium diluent. The fuel was 15.7 wt% enriched U/sup 235/ and the core contained 18.2 vol% sodium and 12.68 vol% stainless steel. The experimental program was designed to measure the effect of the material replacement on spectral indices, which consisted of the standard fission ratios, foil irradiations, and a … more
Date: January 1962
Creator: Gasidlo, J. M.; Long, J. K. & McVean, R. L.
Partner: UNT Libraries Government Documents Department
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MOLTEN-SALT REACTOR PROGRAM PROGRESS REPORT FOR PERIOD FROM MARCH 1 TO AUGUST 31, 1961

Description: The Molten Salt Reactor Experiment design, component development, and engineering analysis is discussed. Materials studies for the Molten-Salt Reactor Program including metallurgy, in-pile tests, chemistry, engineering research, and fuel processing are described. (M.C.G.)
Date: January 19, 1962
Partner: UNT Libraries Government Documents Department
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Calculation of Distance Factors for Power and Test Reactor Sites

Description: >Reference information and guidance on procedures and basic assumptions related to reactor siting are presented which can be used to calculate distance requirements consistent with current siting practices. A single method of competing distances and exposure for a general class of reactors is giveo. (J.R.D)
Date: January 1, 1962
Creator: DiNunno, J. J.; Anderson, F. D.; Baker, R. E. & Waterfield, R. L.
Partner: UNT Libraries Government Documents Department
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FACILITY FOR PHOTOGRAPHING IN-PILE MELTDOWN EXPERIMENTS IN TREAT

Description: Techniques and equipment were developed for photographing of samples during in-pile meltdown experiments in TREAT. The design and materials for the transparent meltdowm facility are described. The procedures for assemblys insertion in TREAT, removal, and disassembly are outlined. (M.C.G.)
Date: January 1, 1962
Creator: Golden, G.H.; Dickerman, C.E. & Robinson, L.E.
Partner: UNT Libraries Government Documents Department
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Nonequilibrium Ionization in Magnetohydrodynamic Generators

Description: The steady state ionization of a gas in which the electrons are hot and the atoms cool is investigated. The rate equations governing ionization, excitation, recombination, and de-excitation are solved for a model system using rate coefficients appropriate to the Cs atom. Included are all processes involving free electrons as well as spontaneous emission and resonance trapping of radiation. No incoming radiation is assumed, and the system is assumed large compared with a collisional mean free pa… more
Date: January 1, 1962
Creator: BenDaniel, D.J. & Tamor, S.
Partner: UNT Libraries Government Documents Department
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Dissociation and Ionization of H$Sub 2$$Sup +$ by Electrons and Protons

Description: <><DSN>16:009503<ABS>Included are summaries of studies of: DCX-1 operation and performance; DCX-2 design and engineering; plasma physics; vacuum arcs; ion production, acceleration, and injection; plasma theory and computations; magnetics; and vacuum system techniques. Separate abstracts were prepared for the eight sections. (B.O.G.) 9504(Faye unscannable abstract)
Date: January 24, 1962
Creator: Alsmiller, R. G., Jr.
Partner: UNT Libraries Government Documents Department
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SPECIFIC HEAT DATA ANALYSIS PROGRAM FOR THE IBM 704 DIGITAL COMPUTER

Description: A computer program was developed to calculate the specific heat of a substance in the temperature range from 0.3 to 4.2 deg K, given temperature calibration data for a carbon resistance thermometer, experimental temperature drift, and heating period data. The speciftc heats calculated from these data are then fitted by a curve by the methods of least squares and the specific heats are corrected for the effect of the curvature of the data. The method, operation, program details, and program stop… more
Date: January 1, 1962
Creator: Roach, P.R.
Partner: UNT Libraries Government Documents Department
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INDUSTRIAL CRITICALITY MEASUREMENTS ON ENRICHED URANIUM AND PLUTONIUM. PART II

Description: ABS>A series of neutron multiplication measurements made on sub-critical systems containing enriched uranium and plutonium is presented. These measurements involve both aqueous and metal systems. (auth)
Date: January 10, 1962
Creator: Schuske, C.L.; Bell, C.L.; Bidinger, G.H. & Smith, D.F.
Partner: UNT Libraries Government Documents Department
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EBWR Reactor Pressure Vessel Revisions for Instrumentation and Increased Steam Output

Description: The procedures developed and utilized for the addition of connections to the EBWR pressure vessel after three yesrs of intermittent operation at the 20- Mw(t) design heat output are described. Major nozzle connections to the pressure vessel were made during two separated periods and under different conditions of vessel content. The details of the conversion sre discussed under the following topics: nozzle design, preparations, and nozzle installation. Diagrams and photographs are included. Radi… more
Date: January 1, 1962
Creator: Kettles, T.L. & Balai, N.
Partner: UNT Libraries Government Documents Department
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Numerical Analysis of Neutron Resonances

Description: Neutron resonances are analyzed numerically by determining the resonant energies, the total widths, and the neutron widths of the resonances. It was assumed that the total cross section can be represented by the sum of single- level Breit-Wigner formulas, with interference between resonance and potential scattering but no interference between resonances; that the Doppler broadening is represented by a Gaussian function; and that the instrument resolution is represented by a Gaussian function. G… more
Date: January 10, 1962
Creator: Atta, S.E. & Harvey, J.A.
Partner: UNT Libraries Government Documents Department
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Pathfinder Atomic Power Plant Analog Simulator.

Description: The steady-state and dynamlc characterlstics of the Pathfinder systems were simulated on a dual-console Pace Analog Computer. The derivation of the system equations, the assumptions involved, their numerical evaluation, and their conversion to analog circuitry are described. The Pathfinder system is unique because of the internal nuclear superheater, and controlled, forced recirculation. In simulating this system the following major assumptions were maden the reactor is a boiling-water type; mo… more
Date: January 31, 1962
Creator: Crimmins, D. H.; Mohr, D. & Stone, J. T.
Partner: UNT Libraries Government Documents Department
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CHARACTERIZATION OF UO$sub 2$ POWDERS. Fourth Quarterly Report, July 10, 1961-October 10, 1961

Description: Studies are described of UO/sub 2/ powders to determine the relation between properties of the powders and sinterability. The main effort during the period was devoted to correlation of the powder particle size distribution with the sintered density of pellets. The pressure applied during the green forming step of pellet production is shown to have a varied and considerable effect on ceramic particle size distribution in the pellets. (J.R.D.)
Date: January 20, 1962
Creator: Carpenter, J.F.; Kuhlman, C.W. & Nelson, R.A.
Partner: UNT Libraries Government Documents Department
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HEXAFLUORIDES OF MOLYBDENUM, TUNGSTEN AND URANIUM. II. REACTIONS WITH LIQUID AND GASEOUS DINITROGEN TETROXIDE

Description: Molybdenum and tungsten hexafluorides form the solids nitrosylium pentafluoroxymolybdate(VI) and -tungstate(VI), respectively. Uranium hexafluoride gives nitrosylium hexafluorouranate(V) STANOUF/sub 6/!, the same salt that it forms with nitric oxide. (auth)
Date: January 29, 1962
Creator: Geichman, J. R.; Smith, E. A.; Swaney, L. R. & Ogle, P. R.
Partner: UNT Libraries Government Documents Department
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HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 1

Description: Four runs were conducted in the Zirflex-Sulfex headend hot cell equipment. Prototype PWR blanket rods, Zircaloy2 clad UO/sub 2/, irradiated from 159 to 356 Mwd/t and decayed 2 years, were declad in boiling 6 M NH/sub 4/F-l M NH/sub 4/NO/sub 3/, terminating with a F/Zr mol ratio of 7 in the spent decladding solution. Average decladding time was 1.5 hr, leaving end cap residues of about 5 g per pin. At the end of the decladding, maximum loss of uranium and plutonium to the decladding solution was… more
Date: January 11, 1962
Creator: Goode, J.H. & Baillie, M.G.
Partner: UNT Libraries Government Documents Department
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