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An Automatic Analyzing Monitor for Reactor Effluent Cooling Water

Description: From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."
Date: May 1, 1959
Creator: Rieck, H. G.; Ratcliffe, C. A. & Schwendiman, L. C.
Partner: UNT Libraries Government Documents Department
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Autunite From Mt. Spokane, Washington

Description: Report discussing the coarsely crystalline autunite in granitic rock near Mt. Spokane, Washington. "This report is an abstract of a paper with the same title that is planned for publication in the American Mineralogist."
Date: May 1959
Creator: Leo, G. W.
Partner: UNT Libraries Government Documents Department
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Ax-1, a Computing Program for Coupled Neutronics-Hydrodynamics Calculations on the Ibm-704

Description: The presentation includes a very general outline of the program, a semi- detailed flow diagram which emphasizes the physics and control aspects of the calculation, and then a detailed flow diagram and listing of the program (which is written in Fortran). Explanatory notes accompany thc diagrams. Following the notes on the program, master lists detailing thc roles of the sense switches, sense lights, pauses, and stops are presented. The operating instructions are then given, followed by a sample… more
Date: May 1, 1959
Creator: Okrent, D.; Cook, J. M.; Satkus, D.; Lazarus, R. B. & Wells, M. B.
Partner: UNT Libraries Government Documents Department
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Blackness Theory and Coefficients for Slab Geometry

Description: ''Blackaess theory'' is described as a class of procedures for matching a high order transport approximation in one region to a low order approximation in a second region. The matching conditions are presented as a generalization of the Marshak boundary conditions. The blackness coefficients necessary in setting up the conditions are defined and tables are given for slab geomrtry. A method which allows all regions to be treated by means of the blackness coefficients is developed and applied to … more
Date: May 1, 1959
Creator: Maynard, C. W.
Partner: UNT Libraries Government Documents Department
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CALCULATION OF GROUP CROSS SECTIONS FOR HOT MONOATOMIC MODERATOR WITH VARIABLE FLUX WEIGHTING WITHIN GROUPS, 704 CODE 521/RE 145

Description: This code finds inelastic cross-section matrix elements (transfer matrix) for hot monatomic moderator for multigroup calculations by numeric- analytic double integration of Cohen's formula. Several approximations to the actual neutron density ean be used as weight functions over the velocities of the initial groups. Modified and supplemented results are presented on binary cards and/or tape for direct input into the Argonne Transport Theory Codes or the SNG Code, or for offline output. (auth)
Date: May 1, 1959
Creator: Bareiss, E.H.; Denes, J.E. & Jankus, V.Z.
Partner: UNT Libraries Government Documents Department
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Cushioning Materials for Packaging: Bibliography

Description: In this brief bibliography the emphasis is on new cushioning materials for packaging and on environmental testing and performance of these materials. The survey is not intended to be exhaustive. The following sources were consulted: Technical Abstract Bulletin of the Armed Services Technical Information Agency, Sandia Unclassified Documents Catalog, U. S. Government Research Reports, Technical Information Pilot of the Library of Congress, and Engineering Index. (auth)
Date: May 1, 1959
Creator: Strachwitz, F. comp.
Partner: UNT Libraries Government Documents Department
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The Density of Liquid Plutonium Metal

Description: Measurements were made of the product of surface tension (ϒ) and the contact angle (θ) of liquid plutonium vs solid tantalum and of the density of liquid plutonium (p) as functions of temperature between 655 and 960°C. The following values were obtained: ϒ cos θ = 1030 - (0.967)T d/cm and p = [17.56$sub 7$ - (1.45$sub 1$ x 10$sup -3$)T] ± 0.021 g/cm$sup 3$. A single determination was also made of the liquid density of a plutonium-7.93 atomic percent iron alloy and he following value obtained: p… more
Date: May 1, 1959
Creator: Olsen, C. E.; Sandenaw, T. A. & Herrick, C. C.
Partner: UNT Libraries Government Documents Department
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DYNAMIC BEHAVIOR OF BOILING REACTORS

Description: Eight boiling reactors, BORAX I, II, III, IV, EBWR, LITR, VBWR, and SPERT I,have been operated to date, and a considerable amount of information exists in regard to their tendencies toward self-induced power oscillations. Data are presented on the following characteristics of the oscillations: power, pressure, temperature, reactivity amplitudes, and their rate of change: thresholds, and harmonic content. Results from three techniques of measuring the reactor transfer function are presented: the… more
Date: May 1, 1959
Creator: Thie, J.A.
Partner: UNT Libraries Government Documents Department
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The Electrical Behavior of Fine Wires Exploded by a Coaxial Cable Discharge System

Description: The characteristic square output currert pulse from a discharging coaxial cable has been utilized to explode wires of 1-mil diameter. The primary pulse duration was 3 mu sec and was variable in amplitude to a maximunn of 600 amperes. Voltage and current waveforms were recorded on a high-speed oscilloscope. Resolution of the system is better than 10/sup -8/ sec, thus enabling accurate determination of the resistance history of the malerial being studied. A survey of the behavior of various metal… more
Date: May 1, 1959
Creator: Tucker, T.J. & Neilson, F.W.
Partner: UNT Libraries Government Documents Department
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Euorochemic Assistance: Chemical Technology Division Unit Operations Section Monthly Progress Report, November, 1958. (Sections 1.0, 5.0, 6.0, 8.0 of ORNL CF-58-11-93)

Description: To better understand the solvent extraction process much effort has been and is being expended at ORNL and elsewhere to measure reaction kinetics of the extraction reactions. To date these efforts have been largely unsuccessful, due to the attempt to apply homogeneous reaction kinetics to two-phase systems. An optical method has been devised for analyzing the concentration profile in the vicinity of a quiescent interface during steady-state diffusion at rather large molecular fluxes. The system… more
Date: May 1, 1959
Creator: Shank, E. M.
Partner: UNT Libraries Government Documents Department
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EUROCHEMIC ASSISTANCE: CHEMICAL TECHNOLOGY DIVISION UNIT OPERATIONS SECTION MONTHLY PROGRESS REPORT, DECEMBER 1958. (SECTIONS 5.0, 6.0, 8.0)

Description: A study of the equiibrium sorption isotherms and rates of U sorption on Dowex 21K is in progress. Data which show the effects of uranium concentration in solution on resin loading are presented Fuel reprocessing experiments are reported in which efforts were made to reduce Cl- in Darex dissolver solution to < 350 ppm for the extraction phase. The best method of Cl/sup -/ reduction appears to be operation with a down draft condenser and an air sparge. A check- out dissolution min in the 6 in. gl… more
Date: May 1, 1959
Creator: Shank, E M
Partner: UNT Libraries Government Documents Department
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EUROCHEMIC ASSISTANCE: CHEMICAL TECHNOLOGY DIVISION UNIT OPERATIONS SECTION MONTHLY PROGRESS REPORT, NOVEMBER 1958. (SECTIONS 1.0, 5.0, 6.0, AND 8.0 OF ORNL CF-58-11-93)

Description: The extraction reaction kinetics and the liquid diffusivities are being studied by measuring the concentration profile in a column of liquid containing an interface. The determination of the equilibrium sorption isotherms and rates of sorption of U on Dowex 21K is reported. Flowsheet development and modification are reported for the Darex process. U was shown that the hydrochlorination of Zr-U alloy fuels with HCl gas contain- ing CO/sub 2/, H/sub 2/O/, and O/sub 2/ impurities increases the qua… more
Date: May 1, 1959
Creator: Shank, E M
Partner: UNT Libraries Government Documents Department
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Eurochemic Assistance: Chemical Technology Division Unit Operations Section Progress Report, December, 1958. (Sections 5.0, 6.0, 8.0)

Description: In order to make rational predictions of the operating characteristics of uranium anion exchange contactors, an understanding of the mechanism and kinetics of the exchange is necessary. Toward this objective an effort is being made to determine the equilibrium sorption isotherms and rates of sorption of uranium on the anion exchange resin Dovex 21K.
Date: May 1, 1959
Creator: Shank, E. M.
Partner: UNT Libraries Government Documents Department
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EUROCHEMIC ASSISTANCE: MONTHLY PROGRESS REPORT FOR CHEMICAL DEVELOPMENT SECTION B, JANUARY 1959. (SECTIONS 1.0, EXCEPT 1.42, AND 2.0)

Description: An effort is being made to determine the equilibrium sorption isotherms and rates of sorption of U on the anion exchange resin Dowex 21K. In the Darex process investigations included: batchwise Cl/sup -/ removal and feed adjustment, continuous dissolution, feed clarification, filtration rates for solutions, effect of pressure drop and fllter aid on flltration rate, cake washing and removal, properties of solutions, and properties of sands and filter aids. Batch dissolutions of irradiated' Conso… more
Date: May 1, 1959
Creator: Shank, E M
Partner: UNT Libraries Government Documents Department
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Eurochemic Assistance: Monthly Progress Report for Chemical Development Section B, January, 1959 (Sections 1.0, except 1.42, and 2.0)

Description: In order to make rational predictions of the operating characteristics of uranium anion exchange contactors, an understanding of the mechanism and kinetics of the exchange is necessary. Toward this objective an effort is being made to determine the equilibrium sorption isotherms and rates of sorption of uranium on the anion exchange resin Dovex 21K.
Date: May 1, 1959
Creator: Shank, E. M.
Partner: UNT Libraries Government Documents Department
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EUROCHEMIC ASSISTANCE PROGRAM: STATUS REPORT AS OF APRIL 1, 1959

Description: The status of the Eurochemic Plant, Mol, Belgium, is summarized, and the Eurochemic organization is given. The anticipated United States assistance through June 1959 is listed. (auth)
Date: May 1, 1959
Creator: Nicholson, E L
Partner: UNT Libraries Government Documents Department
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Evolution of Environmental Testing

Description: Presented at Inst. of Environmental Engineers STAMeeting!, Chicago, April 1959. A brief discussion is presented of the progress over the last seven years of the environmental laboratory at Sandia Corporation. (W.L.H.)
Date: May 1, 1959
Creator: Hooper, R. S.
Partner: UNT Libraries Government Documents Department
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An Experimental Evaluation of the Radiation Protection Afforded by a Large Modern Concrete Office Building

Description: Abstract: "An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fallout. Pocket ionization chambers were used for measurement of the radiation-field strength. Fallout was simulated with distributed and point-source configurations of Co-60 and Ir-192 sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with exp… more
Date: May 1, 1959
Creator: Batter, J. F., Jr.; Kaplan, A. L. & Clarke, Eric Thacher
Partner: UNT Libraries Government Documents Department
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An Experimental Evaluation of the Radiation Protection Afforded by a Large Modern Concrete Office Building

Description: An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fall-out. Pocket ionization chambers were used for measurement of the radiation-field strength. Fall-out was simulated with distributed and point-source configurations of Co/sup 60/ and Ir/sup 192/ sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with ex… more
Date: May 1, 1959
Creator: Batter, Jr., J. F.; Kaplan, A. L. & Clarke, E. T.
Partner: UNT Libraries Government Documents Department
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Experimental Gas-Cooled Reactor: Preliminary Hazards Summary Report

Description: From introduction: This report describes progress during the first quarter on all phases of the ANPP Code Development Program, Pressurized Water Task. The objective of this program is the development of a nuclear physical model and its calculation code for pressurized-water-cooled and moderated reactors to predict accurately reactivity, rod positions, and power distributions at operating temperatures, and reactor life from a nuclear standpoint.
Date: May 1959
Partner: UNT Libraries Government Documents Department
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Fallout From Nuclear Tests at the Nevada Test Site

Description: Presented at the Hearings on Fallout before the Joint Committee on Atomic Energy, May 5-8. 1959. About one megaton of energy from fission has been released at the Nevada Test Site from nuclear test detonations. The total tesultant fission product activity, if measured at one hour after formation, would have been about 400 to 600 billion curies. There was nothing that could be done to lessen the production of radioactive isotopes from a fission reaction thus the utmost care and skill were requir… more
Date: May 1, 1959
Creator: Dunning, G. M.
Partner: UNT Libraries Government Documents Department
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FINAL SPECIFICATIONS FOR GOVERNMENT-PURCHASED EQUIPMENT FOR ARGONNE LOW POWER REACTOR (ALPR)

Description: The final specifications for equipment for the ALPR were prepared from original bid specifications, proposals submitted on equipment purchased, and purchase orders. Each specification includes data pertaining to the equipment purchased, revisions made during the shop fabrication, reference drawing lists vendor's name, and purchase order numbers. (A.C.)
Date: May 1, 1959
Creator: Hamer, E.E. & Hooker, H.H.
Partner: UNT Libraries Government Documents Department
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