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Chemical Technology Division Annual Progress Report, May 31, 1968

Description: Report documenting the ongoing research of the Oak Ridge National Laboratory's Chemical Technology Division. This report includes tables, diagrams, graphs, and articles related to chemical technology.
Date: September 1968
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Fast Reactor Concepts

Description: Report describing the performance characteristics of gas-cooled fast reactors, which compare well with those of sodium-cooled fast reactors. With oxide fuel and helium, CO2, and SO2 coolant at pressures of 1000 to 1500 psia, the reactors have slightly higher breeding ratios than comparable sodium-cooled reactors.
Date: September 1964
Creator: Oak Ridge National Laboratory. Reactor Division. Gas-Cooled Reactor Project.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Annual Progress Report, May 31, 1961

Description: Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.
Date: September 21, 1961
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Fifth Quarter, July-September 1960

Description: From introduction: "this is the fifth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: September 1961
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Seventh Quarter, January-March 1961

Description: From introduction: "This is the seventh of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: September 1961
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Annual Progress Report, July 1, 1960

Description: Report documenting ongoing research and development undertaken by the Metallurgy Division of the Oak Ridge National Laboratory.
Date: September 30, 1960
Creator: Oak Ridge National Laboratory. Metallurgy Division.
Partner: UNT Libraries Government Documents Department
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Fission-Product Release from UO2

Description: Release of fission products from UO2 with emphasis on fuel elements operated at higher surface temperatures and lower external pressures than those for pressurized-water systems.
Date: September 13, 1960
Creator: Cottrell, W. B.; Culver, H. N.; Scott, J. L. & Yarosh, M. M.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Second Quarter, October-December 1959

Description: From introduction: "This is the second of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: September 1960
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: February-April 1957

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress of the Homogeneous Reactor Project. Progress of operations, design, development, and analysis is presented. This report includes tables, illustrations, and photographs.
Date: September 3, 1957
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Ferguson, D. E. et al.
Partner: UNT Libraries Government Documents Department
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Operation of the ORNL Graphite Reactor and the Low-Intensity Test Reactor — 1955 LITR Flux Traverses

Description: The ORNL Graphite Reactor operated very well during 1955. The downtime was low, only 8.6%. The fuel in the bonded slugs did not perform as well in 1955 as in 1954. Much of the trouble was undoubtedly due to growth of slugs which were not beta-transformed. It is known that some slugs had grown over 1/2 in. The automatic central system installed in 1954 continued to operate satisfactorily. The cooling system gave minor trouble when one of the 900-hp fan meters had to be replaced because of shorts… more
Date: September 10, 1956
Creator: Rupp, A. F. & Cox, J. A.
Partner: UNT Libraries Government Documents Department
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A Physical Property Summary for Fluoride Mixtures

Description: This report presents a summary of certain physical properties that have been determined experimentally on the fluoride mixture that have been formulated at ORNL (Rers. 1, 2). These properties include the density, enthalpy, heat capacity, heat of fusion, thermal conductivity, viscosity, Prandtl number, electrical conductivity and surface tension. In addition to the experimental data, values have been predicted for the heat capacity and density of the other mixtures from the correlations of these… more
Date: September 5, 1956
Creator: Cohen, S. I.; Povers, W. D. & Greene, N. D.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1956 [Declassified Version]

Description: Progress report of the Oak Ridge National Laboratory Aircraft Nuclear Propulsion Project providing updates on various projects, experiments, and other work. This report includes summaries of project activities in: aircraft reactor test design, ART physics, ART instruments and controls, component development and testing, procurement and construction, ART, ETU, and in-pile loop operations, phase equilibrium studies, chemical reactions in molten salts, physical properties of molten materials, prod… more
Date: September 4, 1956
Creator: Jordan, W. H.; Cramer, S. J.; Miller, A. J. & Savelainen, A. W.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1956 [Secret Version]

Description: Progress report of the Oak Ridge National Laboratory Aircraft Nuclear Propulsion Project providing updates on various projects, experiments, and other work. This report includes summaries of project activities in: aircraft reactor test design, ART physics, ART instruments and controls, component development and testing, procurement and construction, ART, ETU, and in-pile loop operations, phase equilibrium studies, chemical reactions in molten salts, physical properties of molten materials, prod… more
Date: September 4, 1956
Creator: Jordan, W. H.; Cromer, S. J.; Miller, A. J. & Savelainen, A. W.
Partner: UNT Libraries Government Documents Department
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The Influence of End Mirrors, High Density and Long Tube Length on Radial Diffusion

Description: Diffusion in an arc plasma across a magnetic field is investigated. The geometry is similar to that reported in ORNL-1890 but with the addition of magnetic mirrors on the ends of the arc chamber. It is shown that mirrors do not eliminate the "short circuit" effect. Comparison of the e-folding length, rₒ, of the radial ion density with and without mirrors, affords a direct measurement of ℓ/λ where ℓ is the arc length and λ the mean-free-path. In addition rₒ is independent of gas pressure with mi… more
Date: September 22, 1955
Creator: Simon, Albert
Partner: UNT Libraries Government Documents Department
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Statistical Evaluation of Methods for the Analysis of Dibasic Aluminum Nitrate (DIBAN)

Description: The indicated methods for determining the following constituents of Diban, which is an aqueous solution of dibasic aluminum nitrate, Al(OH)2NO3, were evaluated statistically: 1aluminum by gravimetric, volumetric, and spectrophotometric procedures, 2. basicity (hydroxyl value) by formation of an aluminum complex and titration of the free acid with standard alkali solution, 3. total nitrogen by the Kjeldahl method, 4. ammonia by the Kjeldahl method, and 5. nitrates by means of a cation-exchange r… more
Date: September 16, 1955
Creator: Surak, J. G.; Thomason, P. F. & Haaen, H. P.
Partner: UNT Libraries Government Documents Department
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Determination of Corrosion Products and Additives in Homogenous Reactor Fuel II. Polarographic Determination of Chromium

Description: A satisfactory ion-exchange-polarographic method was developed for the determination of either chromium(VI) or total chromium in Homogeneous Reactor fuels. Total chromium is determined as chromium (VI) , i.e., chromate, and in the same way as is chromium(VI), after chromium in the lower valence states is oxidized to chromate by potassium permanganate. Chromate is separated from all interfering metal ions in the fuel by ion exchange on a Dowex 50 resin column. The Chromate in the effluent is det… more
Date: September 13, 1955
Creator: Horton, A. D. & Thomason, P. F.
Partner: UNT Libraries Government Documents Department
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The Effects of Reactor Irradiation of Thorium-Uranium Alloy Fuel Plates

Description: Several plates of 98.7% Th - 1.2% U 235 (clad in aluminum) were irradiated in the MTR for an integrated flux of 2.6 x 10 21 neutrons/cm2. Although these samples represent an early development in bonding of aluminum to thorium and there are better methods at present, the bond proved to be quite strong and both clad and core were dimensionally stable under irradiation. The production of uranium 233 was as much as theory would indicate and the total amount of fissionable material material after ir… more
Date: September 7, 1955
Creator: Carrell, R. M.
Partner: UNT Libraries Government Documents Department
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ORNL Metal Recovery Plant Processing Clementine Reactor Fuel Elements: Terminal Report

Description: This report presents data obtained from processing 33 Clementine Reactor fuel elements in the ORNL Metal Recovery Plant to recover approximately 15 kg of plutonium and 0.16 g of americium.
Date: September 7, 1955
Creator: Matherne, J. L.; Brooksbank, R. K.; Campbell, D. O.; Chandler, J. M.; Rylton, C. D.; Leuse, R. E. et al.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Progress Report for Period Ending April 30, 1952

Description: This quarterly progress report discusses ongoing work at the Metallurgy Division at the Oak Ridge National Laboratory. Topics discussed include thorium research, the preferred orientation of uranium, studies in the ceramics laboratory, the homogenous reactor program, studies in the x-ray laboratory, studies in the metallographic laboratory, the experimental plate-cladding program, and fuel and control element fabrication.
Date: September 22, 1952
Creator: Frye, John H., Jr., 1908-2001 & Bridge, W. H.
Partner: UNT Libraries Government Documents Department
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A Countercurrent Solid-Liquid Contactor for Continuous Ion Exchange

Description: From abstract: "A continuous countercurrent solid-liquid contactor has been developed which retains the desirable features of the conventional fixed bed and gains the advantages of countercurrent flow. It can be adapted to many solid-liquid mass-transfer processes such as ion exchange, silica gel adsorption, and ore leaching."
Date: September 19, 1952
Creator: Higgins, I. R.
Partner: UNT Libraries Government Documents Department
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