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Upper Atmosphere Monitoring Program. Progress Report No. 6 Covering period November 1, 1958 to January 31, 1959. Report No. 1903

Description: Programs of research into the physical parameters involved in the collection of airborne radioactive particles and the development, fabrication, and calibration of balloon-borne particle sampling equipment to implement the precise determination of stratospheric particle concentration and particle size distribution are reported. A two-stage rectangular jet impactor which collects airborne particles by impingement on a flat plate and is designed to obtain data on size distribution was fabricated.… more
Date: May 1, 1959
Creator: Baumstark, J;; Torgeson, L;; Stern, S;; Schekman, A; & Zeller, W
Partner: UNT Libraries Government Documents Department
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Progress Report No. 54 for the Period through April 30, 1959

Description: This is the fifty-fourth progress report of the Laboratory for Nuclear Science at the Massachusetts Institute of Technology. Progress reported covers the period for Physics and Chemistry through April 30,1959. Progress is reported on: (1) Chemistry of the fission elements group, (2) Nuclear chemistry (inorganic) group, (3) Nuclear chemistry (organic) group, (4) Cosmic ray group, (5) High energy accelerator physics group, (6) Bubble chamber group, (7) Liner acceleratory group, (8) Rockefeller ge… more
Date: May 1, 1959
Partner: UNT Libraries Government Documents Department
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Report of Fire in Laboratory Hood, Wing I, Building 4500

Description: The fire involved approximately 30 liters of isopropyl alcohol as a result of the ignition of about 16-18 liters of isopropyl alcohol and a slurry of thoria and ammonium nitrate in a 20-liter glass carboy. This material was undergoing a volume reduction by boiling in a floor-type metal hood with Plexiglas sides and 3 sliding door on the front of ordinary glass. The alcohol vapor was vents directly into the hood (Fig1.)
Date: May 22, 1959
Creator: Lain, J. E. & Hungerford, T. W.
Partner: UNT Libraries Government Documents Department
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Sizes of U. S. Steam- Electric Plants

Description: At the present time, plants in the 100-500Mv size range are more numerous and carry the greatest portion (over 50%) of the total steam-electric plant load in the U.S. utilities industry. The contribution of plants of over 1,000-Mv capacity is increasing more rapidly than any other size clarification and at present represents about 10% of the total capacity. By 1962 the TVA will have six plants with capacities of over 1,000-Mv. The largest steam-electric plant in the U.S. is the TVA plant at Kin… more
Date: May 26, 1959
Creator: Robertson, R. C.
Partner: UNT Libraries Government Documents Department
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Uranyl Sulfate-Dovex 21K Anion Exchange: A Literature Survey, Review of Preliminary Data and Outline of a Proposal Experimental Program

Description: The system Dovex 21K and aqueous uranyl sulfate solutions were studied in the solution compositions range: 0-0.005 mol/liter uranyl sulfate, 0.15 mil/liter total sulfate, 0.02 mol/liter H2SO4 (pH 2).It is shown that UO3SO4 and/or UO2(SO4)2-/2 are sorbed on the resin to form R2UO2(SO4)2. It is surmized that these same species are also involved at high uranyl concentrations and pH 2 it is suggested that U2O5SO4, U2O5(SO4)2-/2, and R2U2O3SO4 species may be involved.
Date: May 14, 1959
Creator: Jury, S. H. & Adams, J. B.
Partner: UNT Libraries Government Documents Department
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Problems in Accountability Measurements Associated with the Interim Chemical Processing Program

Description: Available knowledge of precision limits in S.S. accountability measurements and/or calculations by reactor and chemical processing groups is surveyed and summarizes. Experience in comparisons of reactor (production and research) calculations versus chemical plant accountability measurements is also reported. A general tentative conclusion is that available precisions (+/- 0.54 to +/- 0.78% ) in chemical plant measurements is also reported. A general tentative conclusion is that available precis… more
Date: May 28, 1959
Creator: Arnold, E. D. & Gresky, A. T.
Partner: UNT Libraries Government Documents Department
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Reprocessing of ARE Fuel, Volatility Pilot Plant Runs E-1 and E-2

Description: After two batches (~ 340 kg) of fluoride salt from the ARE were reprocessed, pilot plant operations were terminated because of a leak through which an estimated 780 g of uranium (as UF6) escaped. Of the 21 kg of highly enriched uranium in the feed, 93.12% was collected as UF6 product, 0.13% represented measured losses, and 3.72% was unaccounted for (leak). An additional 3.03% was reclaimed from NaF beds and equipment washes. The product met both chemical purity and activity specifications for … more
Date: May 11, 1959
Creator: Culler, F. L.
Partner: UNT Libraries Government Documents Department
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The Development of a Fluidized Bed Reactor for the Fluorox Process: Unit operations Monthly Status Reports for the Period November, 1958, Through May, 1959

Description: Results of four experiemental runs in the Fluorox fluidized bed reactor system are reported. The engineering feasibility of UF6 production from UF4 by use of dry air of O2, 2UF4 + O2 = UF6 + UO2F2, in an Inconel fluidized bed reactor at 800-850°C was demonstrated in two experimental tests in which greater than 90% of the theoretical amount of UF6 was collected or measured. Two runs made with crude UF4 (produced from unpurified mill concentrate) as the feed material, showed that UF6 could be pro… more
Date: May 26, 1959
Creator: Bresee, J. C.; Scott, C. D. & Horton, R. W.
Partner: UNT Libraries Government Documents Department
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Nuclear and Radiation Hazards Evaluation of SRE Fuel Processing and Storage

Description: Nuclear and radiation hazards have been investigated for all phases of operation to be carried out in the mechanical decladding of SRE fuel elements. The SRE fuel is 2.8% enriched with a maximum burnup of 1,000 Mvd/ton and minimum cooling of 120 days. Each element contains 9 kg of uranium metal (~2 kg U-235) and is made up from 84 slugs (3/4"D x 6'"), clad with (10 mil wall) stainless steel tubing. It is planned to ship the fuel from Santa Susana, California, to Oak Ridge in the modified PAR l… more
Date: May 20, 1959
Creator: Suddath, J. C.
Partner: UNT Libraries Government Documents Department
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Brief Review of Heat Transfer Problems Encountered in the Production of Magnetic Fields

Description: The design of internally cooled electrical coils for the production of high frequency intensity magnetic fields presents many new aspects and combinations of the familiar modes of heat transfer. However, the customary methodology appears to be sufficient for preliminary analysis and understanding of those problems. This methodology comprises the derivation of a qualitative, approximate equation expressing the relative performance of the various parts of a system, followed by an examination of … more
Date: May 25, 1959
Creator: Alexander, L. G.
Partner: UNT Libraries Government Documents Department
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Volatility: Fluorinator Design FV-100, Zr-U Fuel Element Processing Phase

Description: Volstility Pilot Plant Mark III Fluorinator will be a double-chamber type vessel, each chamber 2-1/2ft. by 16in. o.d. separated by a 5 in. pipe 15 in. long. ASME flanged and dished heads will be used for the chamber tops and conical sections with a 60º apex angle for the chamber bottoms. A new furnace designed to maintain the complete lower chamber (molten salt + freeboard) above melt temperature will eliminate past experiences of salt solidification on the wall, heads, and in or on the interna… more
Date: May 28, 1959
Creator: Ruch, J. B.
Partner: UNT Libraries Government Documents Department
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Design Criteria for a Pile Oscillator

Description: In the use of a reactor as a device to measure neutron cross sections, the pile oscillator is often employed because of its much higher sensitivity compared to that available in static reactivity measurements. The factor limiting the available in static reactivity measurements. The factor limiting the available sensitivity is the generation of random noise, which originates in the statistical nature of the chain reaction. In other words, the nuclear reactions which maintain the chain reaction d… more
Date: May 25, 1959
Creator: Dresner, Lawrence
Partner: UNT Libraries Government Documents Department
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Determination of Thickness of Oxide Film on Phosphor Bronze

Description: The thickness of an oxide film on phosphor bronze helices was determined by first establishing the oxygen content of the helix "as received" and after cleansing with nitric acid. Based on the assumption that the difference between these two values was the oxygen in the film, and that the film consisted entirely of cupric oxide, the thickness of the film was calculated from the density of cupric oxide, weight of the film, and surface area of film. A value of 1080 A was calculated as the thicknes… more
Date: May 19, 1959
Creator: White, J. C.
Partner: UNT Libraries Government Documents Department
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High-Frequency Titration as Applied to the Determination of Thorium, Uranium, Sulfate, and Free Acid. Parts I Through V.

Description: The technique of high-frequency titrimetry has been applied to the determination of thorium, uranium, sulfate, and free acid. In Part I of this report, the reproducibility of the method for the titration of standard solutions which contained 50mg of thorium in the absence of interferences is established. The coefficient of variation of the method, under these conditions, was found to be less than one per cent. In Part II, the effect of uranium on the high-frequency titration of thorium, as well… more
Date: May 11, 1959
Creator: Menis, Oscar
Partner: UNT Libraries Government Documents Department
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Flame Photometric Determination of Iron Parts I, II, III and IV

Description: A study was made of a method for the flame photometric determination of iron. In Part I of this report, the flame emission spectrum of iron, measured by means of a Beckman Model DU spectrophotometer with a flame attachment, is compated to that measured with an ORNL high-sensitivity, recording, single-beam instrument, in order to determine which instrument is best suited for this application. Although it was found that the Beckman product has the higher resolving power over the wavelength region… more
Date: May 6, 1959
Creator: Menis, Oscar
Partner: UNT Libraries Government Documents Department
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Thermodynamic Properties of Dilute Aqueous Hydrochloric Acid Solutions at Elevated Temperatures from Electromotive Force Measurements

Description: A study of the thermodynamic properties of dilute aqueous hydrochloric acid solutions at elevated temperatures by an electromotive force method was undertaken for several reasons. First, a great need for fundamental information at elevated temperatures was evident from the growing number of industries making use of aqueous solutions at elevated temperatures. Second, the use of the hydrogen electrode against the silver-silver chloride electrode in dilute hydrochloric acid solutions promised to g… more
Date: May 1959
Creator: Greeley, Richard Stiles
Partner: UNT Libraries Government Documents Department
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Operation of the HRT Mockup with Boiling Fuel in a Titanium Pressurizer, Run CS-23

Description: The 0.045m UO2SO4, 0.036m CuSO4, 0.025 m H2SO4 solution (HRT fuel composition) was chemically stable during 1, 866hr of operation at 280ºC and 1500 psi. The system was pressurized by boiling a 0.4 gpm stream of the fuel in a titanium heat exchanger at 313ºC.
Date: May 19, 1959
Creator: Korsmeyer, R. B. & Harley, P. H.
Partner: UNT Libraries Government Documents Department
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Eurochemic Assistance Program: Status Report as of April 1, 1959

Description: Considerable delay has occurred in getting ratification of the Eurochemic charter by 80% of the participating nations. The French, who were not expected to ratify the charter until an elected government was again established , actually ratified under de Gaulle late in 1958.
Date: May 5, 1959
Creator: Nicholson, E. L.
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: 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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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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The Rhode Island and Providence Plantations Atomic Energy Commission Nuclear Science Center Volume II - Safeguard Report

Description: This report presents the description and safeguard evaluation of an open pool research and test reactor rated at one megawatt. The reactor is being proposed by the General Electric Company to the Rhode Island and Providence Plantation Atomic Energy Commission.
Date: May 20, 1959
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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Measurement of the Nuclear Materials Content of Non-Production Fuels

Description: In considering the problems associated with the measurement of SSNM content of Non-Production Fuels, two distinct problems are apparent. The first is the technical problem of obtaining highly accurate measurements in a complicated chemical and physical system. The second is the administrative problem of choosing a measurement system which provides a basic of financial settlement acceptable to both the seller (reactor operator) and the buyer (Commission).
Date: May 25, 1959
Creator: Schneider, R. A.
Partner: UNT Libraries Government Documents Department
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The Effect of Solution and Vessel Thermal Expansion on Volume Measurements in the Chemical Processing Department

Description: The major portion of transfers and inventory in the Chemical Processing Department are dependent on volume measurement. Good volume measurements are therefore essential to good SS material control. Considerable attention has been given to the volume problem especially on primary transfer points. Document HW-57888 discusses the biasing effect pf temperature on manometer oil. HW- 57866 given the procedure for vessel calibration. Other undocumented correspondence has discussed recent calibrations … more
Date: May 22, 1959
Creator: Johnson, W. R.
Partner: UNT Libraries Government Documents Department
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