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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 problem, including detailed information on input data. The theoretical discussion has been kept primarily in the appendices, and is generally in outline form with references, rather than in full exposition. (auth)
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 two region cells. Numerical results are compared with other approximations in situations typical of those encountered in resonance capture and thermal utilization calculations. (auth)
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 = [16.88 - (1.36$sub 9$)T] ± 0.012 g/cm$sup 3$.
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 rod oscillation, the reactivity step, and the autocorrelation methods. Quantitative definitions of instability are introduced. Theoretical annlysis of these reactors' kinetic behavior, based on a simple model where steam void feedbacks dominate, shows an adequate understanding of many of the phenomena, some even quantitntively. It is concluded that it is possible within the framework of existing experimental and theoretical boiling reactor dynamic technology, to design these reactors with reduced instability limitations on the power, and obtain power densities in excess of the current 50 kilowatts/liter of core. (auth)
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 metals is presented, and the results of certain parameter studies, such as, geometry, external environment, and current density, are discussed. It is shown that end effects contribute to the measured length of the sample, and that the energy to burst is dependent on current density. A new experimental system capable of producing square current pulses with an amplitude of 2000 amperes is described. (auth)
Date: May 1, 1959
Creator: Tucker, T.J. & Neilson, F.W.
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. glass dissolver with a prototype APPR fuel element is reported, and data on dissolution time and composition of reacted products are given. Data on filtration rates for Darex solutions expected in large-scale operations are tabulated, and graphs illustrating the effects of pressure drop and filter aids on filtering rates are presented. Tests on washing U from filter cakes indicate that U can be removed to any desired level. Viscosity, density. and boiling points as a function of temperature or pressure were determined for two Darex solvent extraction feed solutions; data are presented grahically, and results of chemical analyses are tabuated. Demonstation runs for Sulfex and Zirflex dejacketing flowsheets were made. Results indicate that parts of the Sulfex flowsheet map have to be changed to prevent core losses from fluoride contamination. Results from the Zirflex demonstration are being compiled. Design of the SRE decanning device was completed and sub mitted to vendors for bids; also the design of a prototype fuel bundle to serve as an inexpensive substitute in chopping and leaching studies is reported. Preliminary shearing studies with the 120 ton hydraulic Manco shear indicate that its usefulness is limited, and criteria for a large shear for spent fuel bundles are being written. Darex-type solvent extraction studies using hexane are reported, and U …
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 quantity of HNO/sub3/ insoluble U losses in the uranium chloride product. During the dissolution of spent enriched oxide fuel cores in a dissolver geometricslly safe only in the bottom dissolution area the dissolution off-gas may entrain critical amounts of fine undissolved fuel particles to the enlarged non-critically safe upper portion of the dissolver. Preliminary tests were made to determine the likelihood of fuel fines being entrained in this manner during the dissolution. Solvent extraction studies are being made to assist the Hanford Atomic Products Operation to adapt the Redox process for the recovery ot U from spant stainless steel-type power reactor fuels. Preliminary hot cell tests of the Zirflex and Sulfex flowsheets -Here completed. Batch dejacketing and core dissolution of each of sixteen PWR blanket fuels (UO/ sub 2/ pellets clad with Zircaloy-21 with burnups from 250 to 2500 Mwd/ton were made. A series of experiments was made to determine the amount of fission products evolved when different types of wastes were calcined to dryness. (W.L.H.)
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' Consolidated Edison Fuel and PWR blanket pins were made to demonstrate the Sulfex and Zirflex dejacketing flowsheets, respectively. Dissolution studies to obtain rate and penetration data for UO/sub 2/ in HNO/sub 3/ solutions were begun. Preliminary shearing studies with the 120 ton hydraulic Manco shear with a prototype fuel bundle showed that a line contact shear closes the fuel bearing tubes to an extent detrimental to good leaching. A series or experiments was performed to determine the amount of fission products evolved when different types of wastes were dried and calcined. (W.L.H.)
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 exposed basement walls and an external wing with a buried basement. Roof studies were made on an internal wing with a full basement and on the east end of wing A, which has a thin-roof construction. The thick-roof construction of 8 in. of concrete and 2 in. of rigid insulation covers all the building except the east end of wing A, which has 4 in. of concrete and 2 in. of insulation."
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 exposed basement walls and an external wing with a buried basement. Roof studies were made on an internal wing with a full basement and on the east end of wing A, which has a thin-roof construction. The thick-roof construction of 8 in. of concrete and 2 in. of rigid insulation covers all the building except the east end of wing A, which has 4 in. of concrete and 2 in. of insulation. (auth)
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 required ia the conduct of the tests to minimize the deppsition of the activity outside the Test Site. A summary of the data on fall-out from nuclear detonations at the Nevada Test Site is presented. (auth)
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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FLAME PHOTOMETRIC DETERMINATION OF IRON. PARTS I, II, III AND IV

Description: An investigation was conducted to compare the flame emission spectrum of Fe as recorded by the Beckman DU and the ORNL flame spectrophotometers. It was found that the ORNL instrument is best suited to the application. Optimum operating conditions are described as well as results of investigations to determine interferences. (J.R.D.)
Date: May 1, 1959
Creator: Menis, O
Partner: UNT Libraries Government Documents Department
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GEORGE PROGRAMMING MANUAL

Description: GEORGE is an automatic high-speed electronic digital computer designed and constructed by ANL. Operating features of GEORGE are described, and a practical set of instructions is given that will enable a prospective user to construct codes, operate the machine and its auxiliary equipment, use the basic routines available in the routine library, and decide whether a particular problem is suitable on the basis of capacity, speeds and auxiliary equipment. (W.D.M.)
Date: May 1, 1959
Creator: Kassel, L.
Partner: UNT Libraries Government Documents Department
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Handbook: A Technique for Preparing Desert Terrain Analogs

Description: "A technique is described whereby desert areas selected for terrain comparison are mapped in terms of general terrain factors, geometry factors, ground factors, and vegetation" (p. vii).
Date: May 1959
Creator: Van Lopik, Jack R. & Kolb, Charles R.
Partner: UNT Libraries Government Documents Department
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