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Supplement No. 1. Projections of Costs, 1959-1975 for Nuclear-Conventional Power Plant Cost Study. Conventional Coal Fired Power Plants : 25,000 KW to 325,000 KW for Argonne National Laboratory, Lemont, Illinois

Description: In order to establish a basis for comparing the estimated cost of nuclear power plant designs, a set of general and detailed design considerations for conventional coal-fired power plants was established. Five preliminary designs of conventional coal-fired power plants ranging in size from 25to 325 mw were selected, and cost estimates were prepared. Supplement 1 shows a year by year projection of costs for the period 1959-1975.
Date: July 2, 1959
Creator: Chittenden, W. A.
Partner: UNT Libraries Government Documents Department
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A Regulated Power Supply for a High Current Magnet

Description: Current regulation of a Bitter type electromagnet powered by a 10 kw. motor-generator set has been achieved by control of the generator exciting field. An error signal, obtained by comparing the voltage drop across a series resistor in the magnet circuit with a reference voltage, is fed back with appropriate amplification to the grids of series tubes in the generator field supply. Magnetic fields from 400 gauss to 10 kilogauss in a fixed gap (1.5 in. width and 3.5 in. diameter) are obtainable w… more
Date: July 1959
Creator: Block, Richard B.
Partner: UNT Libraries Government Documents Department
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Determination of the Nil-Ductility-Transition Temperature for A212B Steel Used in the N. S. Savannah Pressure Vessel

Description: The nil-ductility-transition (NDT) temperature, as defined by the Naval Research Laboratory drop-weight test, was determined on the A212B carbon-silicon steel used in the pressure vessel of the N. S. Savannah nuclear reactor. Correlations were made with the Charpy-V-notch impact energy at NDT. Specimens taken at two different thickness location from materials used in the upper closure head of the reactor vessel yielded NDT temperatures of 0 - 20°F which correspond to Charpy-V-notch impact energ… more
Date: July 23, 1959
Creator: Thurber, W. C. & Lamartine, J. T.
Partner: UNT Libraries Government Documents Department
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The Rate of Uranium Sorption by a Strong-Base Anion-Exchange Resin

Description: The rate of uranium sorption by a strong-base anion-exchange resin (Dovex 21K) from a uranyl sulfate solution (U 0.005 M, H2SO4 0.02M, SO4 0.2 M) was studied using a stirred vessel technique and measuring the U235 gamma radiation on each bead. Resin initially in the chloride form and the sulfate for was studied.
Date: July 8, 1959
Creator: Bresee, J. C.
Partner: UNT Libraries Government Documents Department
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Determination of Oxygen in Oxide Films by Neutron Activation Analysis

Description: Preliminary experiments have been conducted to evaluate the use of the nuclear reactions Li6 (n,α)H3 and O16(H13,n)F18 to determine the thickness of oxide films on metals. Sheets of thin paper and of aluminum, imbedded in powdered LiF, were irradiated with pile neutrons at a flux of 6 x 10^11 n/cm^2/sec and counted with an end-window proportional counter. A saturation activity of 1.87 hr F18 of 150 dis/min per microgram of oxygen was observed in the paper, but radioactivity due to impurities ma… more
Date: July 15, 1959
Creator: Winchester, J. W.; Meyer, R. E.; Bate, L. C. & Leddicotte, G. W.
Partner: UNT Libraries Government Documents Department
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Determination of Li6 in Aqueous Solution by Neutron Activation Analysis

Description: A method for determining the concentration of Li6 in aqueous solution has been tested using the nuclear reactions Li6 (n,α)H3 and O16 (H3,n)F18. Annihilation 7 radiation of induced 1.87 hour F18 radioactivity was counted with a well-type scintillation counter, and the radioactivity per millimole of lithium was found to be independent of lithium concentration below about 0.2moles/liter. The sensitivity limit for detecting lithium is less than 0.1 micromole (0.0075 micromole Li6).
Date: July 10, 1959
Creator: Winchester, J. W. & Bate, L. C.
Partner: UNT Libraries Government Documents Department
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Time Dependence of the Beam in the 86-Inch Cyclotron

Description: In the preliminary stages of getting up a time-of-flight system for measuring neutron spectra from proton reactions, a study of the time dependence of the beam in the 86Inch Cyclotron was made. This study revealed the expected bunching of the protons to produce a short burst of beam on each cycle of the 13.4 Mc/s accelerating voltage. In addition to the 13.4 Mc/s structure, however, there was a 360 c/sec modulation of the beam pulses and a complicated pattern built upon that.
Date: July 29, 1959
Creator: Goodman, C. D.
Partner: UNT Libraries Government Documents Department
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Investigation of Mechanical Methods of Scale Removal from HRT Heat Exchangers

Description: Tests were conducted to determine methods of removing scale deposits from the HRT heat exchangers. A mockup of the heat exchanger header was cleared of a deposit of iron rust by reverse flushing at a flow rate below 75 gpm. A tube bundle consisting of 109 1/4in. O.D. x 0.049 in. wall tubes was plugged with rust. Approximately 80% of these tubes were unplugged by using a 70 psi water pressure differential in combination with vibration from a pneumatic rivet gun. No mechanical method was employe… more
Date: July 21, 1959
Creator: Gabbard, C. H.; Eissenberg, D. M.; Moyers, J. C. & Namba, I. K.
Partner: UNT Libraries Government Documents Department
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A Parametric Study of a Gas Cooled Reactor

Description: The results of a parametric study on a gas cooled reactor are reported on herein. The system considered was a helium cooled, UO2 fueled arrangement with the fuel assemblies consisting of clusters of long cylindrical elements, each element covered b a stainless steel jacket. The axial power distribution was assumed to be a "chopped cosine" having an axial peak-to-average power 1.32.
Date: July 24, 1959
Creator: Epel, L. G.
Partner: UNT Libraries Government Documents Department
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PRFR Pilot Leaching Plant - Preliminary Process Design

Description: The preliminary process design of a PRFR pilot leaching plant, which is proposed to be located in Cell B of Building ORNL, is considered. Chemical, physical, and nuclear parameters are investigated in order that the leaching operations may be carried out without any chemical or nuclear hazards.
Date: July 23, 1959
Creator: McLain, H. A.
Partner: UNT Libraries Government Documents Department
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Multiplication Measurements with Highly Enriched Uranium Metal Slabs

Description: A series of neutron multiplication measurements with arrays of 1 by 8 by 10 in. slabs of 93.4% U235-enirched uranium metal have been made to provide data from which safety criteria for the storage of these fissile units can be established. Each slab contained 22.9 kg of U235. A maximum of 125 unites was assembled. The arrays studied were cubic lattices of the units and were usually parallelepipedal in shape.
Date: July 27, 1959
Creator: Mihalczo, J. T. & Lynn, J. J.
Partner: UNT Libraries Government Documents Department
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Decontamination of the PRFR Pilot Leaching Plant - Preliminary Process Design

Description: The Turco 4501 process is recommended for the decontamination of the PRFR pilot leaching plant equipment. The caustic-tartrate-nitric acid process is recommended for the decontamination of the cell and the equipment exterior.
Date: July 23, 1959
Creator: McLain, H. A.
Partner: UNT Libraries Government Documents Department
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Multigroup Diffusion Theory Calculations for Recent Critical Experiments

Description: In connection with the program of the measurement of eta for U233, several critical experiments have been performed by R. Gwin and D. W. Magnuson of ORML with light water solutions of uranyl nitrate (highly enriched in either U233 or U35) in an essentially bare sphere 27 inches in diameter. This report presents the results of two multigroup-diffusion-theory calculations for the above experiments performed by C. B. Mills and associated at Los Alamos. Assumer cross sections, material concentratio… more
Date: July 21, 1959
Creator: Nestor, C. W., Jr
Partner: UNT Libraries Government Documents Department
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Run 300A-B Slurry Run of 300A Pump and Loop

Description: The 300A and loop were operated for 2862 hr with thorium oxide slurry at 1500 psi and 280ºC to determine the effects vane inlet and exit geometries on impeller wear, the wear rate of aluminum oxide bearings in this size pump, and the operating characteristics of the loop. The thoris, a 1600*C-fired oxide, had a mean particle size of approximately 2 u. Average circulating slurry concentration was approximately 450 grams of thorium per kilogram of water and average flow rate was approximately 300… more
Date: July 2, 1959
Creator: Moyers, J. C.
Partner: UNT Libraries Government Documents Department
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Test of Heater and Cooler Concepts for OCR-ORR Loop, Design 4

Description: High heat flux electrical cartridge heaters were tested with direct air cooling under simulated ORR Loop conditions. The cartridges and the heater design were found to be satisfactory. A gas cooled of concentric pipe design utilizing air, water, and air-water mixtures as the coolant was also evaluated and found to be satisfactory.
Date: July 13, 1959
Creator: Kelley, W. H., Jr. & Storto, E.
Partner: UNT Libraries Government Documents Department
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Eurochemic Assistance Program: Comments by FMPC, dated July 6, 1959, on Eurochemic Technical Documents

Description: The nuclear safety portion of this report is inclined to ignore the factors by which safety limits can be increased. It makes no mention of the control that can be exercised by limiting the assay of the U-235 being processed in the plant. From some of the previous reports, it is apparent that this plant is not anticipating processing U-235 of assay greater than approximately 20%. At this value, many of the numbers that are presented in the tables could be increased markedly. Rough examination i… more
Date: July 14, 1959
Creator: Cuthbert, F. L.
Partner: UNT Libraries Government Documents Department
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Zirconium Diboride, Boron Nitride, And Boron Carbide Compatibility with Austenitic Stainless Steel

Description: The compatibility of zirconium diboride, boron carbide, and boron nitride with type 304 stainless steel was evaluated as a function of temperature (1000-1200°C), time (1-3 hr). Appropriate loadings of the boron compounds and stainless steel powder were blended and fashioned into a compact powder metallurgically. Each compact was roll clad into a plate and subsequently heat treated at a temperature equal to the initial sintering temperature. Metallographic examination of the fabricated and heat-… more
Date: July 31, 1959
Creator: Cherubini, Julian H. & Leitten, C. F., Jr.
Partner: UNT Libraries Government Documents Department
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Post-Irradiation Examination of Cored, Edge Loaded, Thoria-Urania Nuclear Fuel

Description: Three edge loaded thoria-urania nuclear fuel samples were assembled into a capsule, irradiated and examined. This irradiation was the first of a series to develop thoria-urania fuel for high heat flux, specific power and burn-up operation in a sodium graphite reactor.
Date: July 15, 1959
Creator: Slosek, T. J.
Partner: UNT Libraries Government Documents Department
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Hydraulic Instability In a Natural Circulation Loop With Wet Steam Generation at 1000 PSIA

Description: Experimental test loops have been used to study the problem of hydraulic stability. The oscillatory behavior of a single-phase and two-phase natural circulation loop has been examined at atmospheric pressures and oscillating modes of operation were studied in terms of heat input.
Date: July 15, 1959
Creator: Levy, S. & Beckjord, E. S.
Partner: UNT Libraries Government Documents Department
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Shielding on a 27,300 SHP Boiling Water Reactor Marine Propulsion System

Description: This report summarizes the radiation and shielding analysis for a 30,000 SHP natural circulation boiling water reactor for ship propulsion. The reactor is proposed for installation in a 60,000 DWT, 18 knot tanker of the T-7 class.
Date: July 25, 1959
Creator: Craig, W. D.
Partner: UNT Libraries Government Documents Department
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Hanford Neptunium Oxalate-Oxide Process Experience

Description: In recent months, relatively large quantities of neptunium-237 have been recovered from Hanford irradiated uranium. The over-all recovery process consisted of 1) isolation from Purex plant solutions by solvent extraction, to yield an impure neptunium nitrate solution contaminated principally with uranium, plutonium, and fission products (2) purification by anion exchange 3) precipitation of neptunium (IV) oxalate; and 4) calcination of the oxalate to yield neptunium (IV) oxide, NpO2. This paper… more
Date: July 1, 1959
Creator: Pollock, C. W. & Schneider, R. A.
Partner: UNT Libraries Government Documents Department
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Suggested Major Equipment for NPR Water Quality Control Labs

Description: Two water quality control labs are being provided for the the NPR. One, a "cold" lab, is located in the183 Building adjacent to the control room. Its primary purpose is to provide facilities for quality control of the output of the filter plant and the demineralizer plant. The other, a "hot" lab, is located in the 190 Building. Its primary purpose is to provide facilities for the quality control of the primary and secondary coolants, and the moderator coolant.
Date: July 30, 1959
Creator: Bainard, W. D.
Partner: UNT Libraries Government Documents Department
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PRTR Total Energy Distribution Calculations

Description: Since the calculation of the PRTR energy distribution was first carried out by J. R. Triplett, the design has become sufficiently fixed to allow a refinement of his values. The present analysis, also, includes a calculation of the fraction of energy which is released in the shroud and process tubers that flows to the primary coolant to the top and bottom shield coolant is taken into consideration. Nuclear data used in the original calculations still appears satisfactory and is, therefore, util… more
Date: July 31, 1959
Creator: Peterson, R. E.
Partner: UNT Libraries Government Documents Department
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