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Tables of Chemical Kinetics : Homogeneous Reactions (Supplementary Tables)

Description: From Preface: "A brief description of the method used in compiling these tables and the limitation of coverage is given in the preface to Supplement 1. A description of the numbering system used is classifying reactions for the tables is given in Supplement 2. The present supplement contains information pertaining to Substitution, Exchange and Elimination reaction types. It is not complete as still more material falling groups is being prepared."
Date: September 15, 1961
Creator: United States. Bureau of Standards.
Partner: UNT Libraries Government Documents Department
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SL-1 Annual Operating Report: February, 1960-January 3, [1961]

Description: The Stationary Low Power Reactor No. 1 (SL-1) was a boiling water reactor demonstration plant for remote military bases. The plant had been operated by Combustion Engineering, Inc. from February, l959 until January 3, 1961 at which time a nuclear excursion rendered the plant inoperable, This report summarizes the of operations of maintenance, test, health and safety, and administrative activities for the year February, 1960 until the incident.
Date: June 15, 1961
Partner: UNT Libraries Government Documents Department
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Design Modifications to the SRE during FY 1960

Description: Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
Partner: UNT Libraries Government Documents Department
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Metallurgical Aspects of SRE Fuel Element Damage Episode

Description: Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.
Date: October 15, 1961
Creator: Ballif, J. L.
Partner: UNT Libraries Government Documents Department
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Investigations of Neutron Penetration in TiH and Steel Slabs

Description: Abstract: A multigroup P1 approximation for hydrogen scattered neutrons has been developed and applied to the study of neutron flux distributions in titanium hydride and steel shield systems.
Date: May 15, 1961
Creator: Karcher, R. H.
Partner: UNT Libraries Government Documents Department
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Conceptual Design and Economic Evaluation of a Steam-Cooled Fast Breeder Reactor

Description: From abstract: This report describes a conceptual design and economic evaluation of 300 and 40 MWe steam-cooled fast breeder reactor power plants performed by NDA under contract with the AEC.
Date: November 15, 1961
Creator: Sofer, G.; Hankel, R.; Goldstein, L. & Birman, G.
Partner: UNT Libraries Government Documents Department
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Mechanical Properties of Zircaloy-2 Weld Metal

Description: Abstract: Zircaloy-2 weld metal, obtained by inert gas non-consumable-electrode welding, was subjected to tensile, strain fatigue, and creep-rupture testing.
Date: April 15, 1961
Creator: Beitscher, S.
Partner: UNT Libraries Government Documents Department
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THE EIGHTFOLD WAY: A THEORY OF STRONG INTERACTION SYMMETRY

Description: A new model of the higher symmetry of elementary particles is introduced ln which the eight known baryons are treated as a supermultiplet, degenerate in the limit of unitary symmetry but split into isotopic spin multiplets by a symmetry-breaking term. The symmetry violation is sscribed phenomenologically to the mass differences. The baryons correspond to an eight-dimensional irreducible representation of the unitary group. The pion and K meson fit into a similar set of eight particles along wit… more
Date: March 15, 1961
Creator: Gell-Mann, M.
Partner: UNT Libraries Government Documents Department
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High Purity Uranium Compounds. Final Report

Description: Uranium-aluminum compounds were prepared by solidsolid reaction of aluminum powder and uranium hydride; x-ray-diffraction patterns showed that single phases of UAl/sub 2/, UAl/sub 3/, and UAl/sub 4/ could be achieved. The uranium-beryllium compound, UBe/sub 1//sub 3/, was prepared by solid-solid reaction of berylllum powder and uranium hydride. The uranium-boron compounds, UB/sub 2/ UB/sub 4/, and UB/sub 1//sub 2/ were prepared by solid reaction, and single borides were obtained; carbon contami… more
Date: January 15, 1961
Creator: Eding, H.J. & Carr, E.M.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program, Progress Report, May 1961

Description: General research and development on water-cooled and sodium-cooled reactors are reported along with specific developments on EBWR, BORAK-V, EBR-I, and EBR-H. Thermal and fast reactor safety studies are summarized in terms of fuel-coolant chemical reactions, kinetics of oxidation and ignition of reactor materials, core meltdown studies, and a sodium vapor pressure furnace. Evaluations were made of improved fast reactors for central station power and of a 50-Mwe Prototype Organic Power Reactor (P… more
Date: June 15, 1961
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report, January 1961

Description: Modifications of EBWR are described, and data from analysis of control- rod operational crud deposit are tabulated. Development and construction progress on Borax V are summarized. Research for ZPR III is reported on a series of uranium oxide critical cores. Comparative data on composition, critical masses, and central fission ratios are tabulated for these assemblies. Developmental work on ZPR-VI, ZPR-IX, and Juggernaut is summarized, followed by a summary of EBR-I operation and development of… more
Date: February 15, 1961
Partner: UNT Libraries Government Documents Department
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REVIEW OF INVESTIGATIONS PERTINENT TO THE PREDICTION OF THE THERMAL BEHAVIOR OF FAST REACTORS UNDER ABNORMAL OPERATING CONDITIONS

Description: Results are summarized for a survey of methods for predicting fuel element and coolant behavior in sodiumcooled fast reactors under abnormal operating conditions. Circumstances prior to, during, and after meltdown are considered, and the behavior of fuel and coolant during transients is discussed. Reactor excursions, theory of fuel element thermal transients, reactor coolant transients in single and two-phase flows, and specific topics such as two-phase flow patterns, two-phase pressure drop, a… more
Date: March 15, 1961
Creator: Beers, F.E.
Partner: UNT Libraries Government Documents Department
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Processing of Uranium Carbide Reactor Fuels. I. Reaction With Water and HCl

Description: High-purity uranium monocarbide reacted with water at 80 deg C to produce a finely divided, brown U(IV) compound, and 92 nfl (STP) of gas per gram consisting of 11 vol% hydrogen, 86 vol% methane, 2 vol% ethame, and 0.6 vol% propane. At 90 deg C, the products were the same, but the reaction rate was higher. Reaction with 5.6 M HCl was slower than with water, but the gaseous products were essentially the same. In preliminary experiments at 80 deg C with UC-UC/sub 2/ mixtures containing less than … more
Date: August 15, 1961
Creator: Bradley, M. J. & Ferris, L. M.
Partner: UNT Libraries Government Documents Department
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THE CORROSION OF ALUMINUM ALLOYS IN HIGH-VELOCITY WATER AT 170 TO 290 C

Description: Short-term corrosion tests with types 1100, 5154, 6061, and X8001 aluminum alloys were conducted in water at flow rates rsnging between 20 and 107 fps and at temperatures between 170 and 290 deg C. Corrosion of the alloys was less dependent on flow rate in the range of 20 to 67 fps than at higher velocities. At temperatures as high as 230 deg C no evidence of localized attack, except for random shallow pitting, was exhibited by these alloys, and all had comparable corrosion rates. At 260 and 29… more
Date: June 15, 1961
Creator: English, J. L.; Rice, L. & Griess, J. C.
Partner: UNT Libraries Government Documents Department
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Atomic and molecular collision cross sections of interest in controlled thermonuclear research

Description: A graphical compilation is presented of atomic and molecular cross sections of interest to controlled thermonuclear research. The cross sections are shown, as a function of energy, for collision processes involving molecular ion dissociation, charge exchange, excitation, ionization, photoionization, scattering, energy loss, and recombination. Pertinent nuclear cross sections are also included. A bibliography is given covering the literature since 1950. (auth)
Date: May 15, 1961
Creator: Barnett, C. F.; Gauster, W. B. & Ray, J. A.
Partner: UNT Libraries Government Documents Department
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Calculated Transient Pressures Due to Impulse and Ramp Perturbations to Ventilating Systems in Buildings 3019, 3026, 3508, and 4507

Description: As part of a general hazard review survey conducted by the Chemical Technology Division of its facilities, transient pressures due to impulse and ramp perturbations to the cell ventilating systems of buildings 3019, 3026, and 4607 and the closed glove box system of 3508 were calculated. From the portions of the pressure curves above atmospheric pressure, volumes of gas outleakage were estimated; thus the amount of activity released can be calculated if an estimate of the activity concentration … more
Date: August 15, 1961
Creator: Perona, J.J.; Dunn, W.E. & Johnson, H.F.
Partner: UNT Libraries Government Documents Department
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WHIRLAWAY--A THREE-DIMENSIONAL, TWO-GROUP NEUTRON DIFFUSION CODE FOR THE IBM 7090 COMPUTER

Description: WHIRLAWAY is an IBM 7090 FORTRAN programmed code for the solution of two- group neutron diffusion equations in xyz geometry. The code was designed to run under control of the IBM 7090 FORTRAN Monitor System on a machine with at least six tape units. The maximum number of mesh points is limited to 12,750. Arbitrary distributions of materials and mesh spacing are permitted. The boundary conditions are either zero flux or zero current at each of the six faces of the reactor, and the code will, if … more
Date: August 15, 1961
Creator: Fowler, T. B. & Tobias, M. L.
Partner: UNT Libraries Government Documents Department
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Design Modifications to the SRE During FY 1960

Description: The means used to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redssign of system components to utilize alteraate coolants such as nitrogen, air, and NaK. The use of kerosene to replace tetralin, where double containment is provided, is discussed. The physical properties are compared, and kerosene is shown to be free of the undesirable characteristics of tetralin. The fuelelement cleaning systsm was redesigned for steam w… more
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
Partner: UNT Libraries Government Documents Department
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INCR-8-Graphite-Fused Salt Compatibility Test

Description: For the purpose of evaluating the compatibility of graphite and INOR-8 in a dynamic fluoride fuel medium, INOR-8 Forced Convection Loop No. 9354-5 was operated 8850 hr. The loop operated at maximum temperature of 1300 deg F and circulated a fluoride fuel of the system LiF--BeF/sub 2/-- UF/sub 4/. Post-test examinations of the graphite and loop components revealed no apparent corrosion or carburization problems. (auth)
Date: June 15, 1961
Creator: Schulze, R. C.; Cook, W. H.; Evans, R. B., III & Crowley, J. L.
Partner: UNT Libraries Government Documents Department
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KINETIC EXPERIMENTS ON WATER BOILERS. "A" CORE REPORT. PART V. CONTAINMENT ASPECTS OF PRESSURE WAVES FROM SOLUTION EXPANSION

Description: A theoretical treatment is made of the stress-strain and plastic flow properties of spherical shells of stainless steel under dynamic loading. The results are used to calculate the response of a homogeneous reactor core to inential pressure pulses. The importance of the duration of the pressure pulse as compared with a natural time or period of the material in plastic as well as in elastic deformation is noted. For a small homogeneous reactor core vessel, the natural plastic "swing time" is fou… more
Date: February 15, 1961
Creator: Greenfield, M.A.
Partner: UNT Libraries Government Documents Department
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VAPORIZATION OF ZIRCONIUM OXIDE

Description: No Description Available.
Date: April 15, 1961
Creator: Nakata, M.M.; McKisson, R.L. & Pollock, B.D.
Partner: UNT Libraries Government Documents Department
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