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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952

Description: This quarterly progress report details ongoing work at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. Topics of discussion include reactor theory and design, shielding research, materials research, appendixes with information on ongoing analytical chemical studies.
Date: August 5, 1952
Creator: Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, W. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination of ORNL Purex Pilot Plant

Description: From abstract: "This report describes the decontamination of Oak Ridge National Laboratory Purex Pilot Plant facilities and presents an appraisal of the decontaminating techniques and reagents which were employed."
Date: May 5, 1952
Creator: Wood, H. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Development Section C Monthly Progress Report July 1959

Description: Nitrate contained in raffinates from Canadian Blind River mills interferes seriously with thorium extraction by secondary amines. With primary amines, however, the effect is negligible and these compounds are the preferred process extractants.
Date: August 5, 1959
Creator: Brown, K. B.; Allen, K. A.; Blake, C. A.; Coleman, C. F.; Crouse, D. J.; Ryon, A. D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation of Transport Cross Sections

Description: Many elements exhibit anisotropic scattering at energies of interest in reactor calculations. A method is presented for the calculation of transport cross sections including the observed anisotropy.
Date: August 5, 1959
Creator: Nestor, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear and Economic Characteristics of several Two-Region Homogeneous Reactors

Description: The nuclear characteristics and fuel costs of a number of aqueous homogeneous reactors have been estimated. Most of the reactors studied were cylindrical, two-region power-breeders variously having between 0 and 300 g/l of thorium in the core and between 500 and 1000 g/l of thorium in the blanket. The results of the calculations, including breeding ration, fuel inventories, doubling times, and net fuel costs, are summarized in this report.
Date: June 5, 1959
Creator: Rosenthal, M. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Review of the Mathematical Formulation of the Problem of Inelastic Neutron Scattering by Polycrystalline Material

Description: A self-contained developmental or the formation of the problem of inelastic neutron scattering by crystals is presented. although nearly all of the methods and results used in the present discussion have appeared in a variety of previously published papers, additional mathematical details are given here which have been found by thee authors to aid in understanding the final results.
Date: June 5, 1959
Creator: Preskitt, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analytical Chemistry Division Semiannual Progress Report for Period Ending April 20, 1954

Description: Progress report of the Oak Ridge National Laboratory Analytical Chemistry Division providing updates on various projects, experiments, and other work in ionic analyses, analytical instrumentation, radiochemical analyses, activation analyses, spectrochemical analyses, inorganic preparations, optical and electron microscopy.
Date: July 5, 1956
Creator: Kelley, M. T.; Susano, C. D. & Raaen, H. P.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C

Description: One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.
Date: May 5, 1962
Creator: Jenks, G. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Low Cost Experimental Neutron Chain Reactor Part 2

Description: Description of cooling, shielding, controls are discussed for 100 kw and 1 Mw operation of a low cost experimental neutron chain reactor.
Date: February 5, 1954
Creator: Abernathy, Fred H.; Barrett, Lawrence G.; Berger, William A.; Dever, John A.; Maurer, John F.; Mesler, Russell B. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fabrication of Heat Exchangers and Radiators for High Temperature Reactor Applications

Description: Two 500-kw fused-fluoride-to-Nak heat exchangers, two 500-kw NaK-to-air radiators, and a 20-tube high-velocity heat exchanger were fabricated for a heat-exchanger development program. A construction procedure, utilizing both inert-arc-welding and high temperature dry-hydrogen brazing, was used successfully on all of the units. The tube-to-header joints were welded and back-brazed; the manifold joints were inert-arc-welded with full penetration; and the tube-to-fin joints were brazed. A detailed… more
Date: July 5, 1955
Creator: Patriarca, P; Slaughter, G. M.; Manly, W. D.; Heestand, R. L.; Clausing, R. K.; Conner, O. K. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Test Summary Report for the Advisory Committee on Reactor Safeguards

Description: The Homogeneous Reactor Test (HRT) is the experimental reactor facility (Frontispiece) being designed and constructed at ORNL as the next step in homogeneous reactor development between the 1-Mv HRE and a "full-scale" power station. The HRT will provide an integrated test at 5 to 10 Mv for the flowsheet and equipment designs on which the full-scale effort will be based. Furthermore, its design is such that several homogeneous systems which require essentially the same operating equipment may be… more
Date: January 5, 1955
Creator: Beall, S. E. & Visner, S.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Strontium Sorption Studies Using Naturally Occurring Ion Exchange Materials

Description: Four naturally occurring materials, namely, vermiculite, variscite, Tennessee rock phosphate, and Florida pebble phosphate, were studied to determine the feasibility of their use in columns for the sorption of strontium from high pH, intermediate-level wastes produced at ORNL. Excepting vermiculite, all materials were found to be effective in strontium removal.
Date: December 5, 1960
Creator: Thomas, K. T.; Jacobs, D. G.; Tamura, T. & Struxness, E. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Transport Calculation of the HFIR Beam Hole Currents

Description: An estimate was made of the beam hole currents to be expected from both the radial and tangential beam holes in the present HFIR design. The angular fluxes required for these calculation were determined by an 18-group, S8 transport calculation (SNG reactor code). Both type beam holes produced thermal neutron currents of 7.5 x 10^10 neutrons/cm^2 sec. at a power level of 100 Mw. The nonthermal component of the beam current was 7.0 x 10^10 and 4.5 x 10^10 neutrons/cm^2 -sec for the radial and tan… more
Date: December 5, 1960
Creator: Claiborne, H. C. & Rakavy, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bellows Failure in Solids Separation Loop of the HRT Mockup

Description: The failure of the valve bellows would appear to be due to a combination of stress corrosion and crevice corrosion. Stress corrosion occurred as evidenced by the transgranular branched cracking found in the bellows and in the base which which was joined to the bellows. It seems probable that chlorides were present, which, along with the residual stresses present in the bellows assembly, created the necessary conditions for stress corrosion to occur. Crevice corrosion occurred probably due to he… more
Date: February 5, 1957
Creator: Kegler, T. M., Jr. & Hammond, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High Pressure Flange Studies

Description: Twenty-five hundred psi ring-type flanges, ring gaskets, bolts, and special connectors were tested for adaptability to the aqueous homogenous reactor. High pressure line closures were studied to obtain empirical data pertinent to the selection or design of a connector capable of withstanding sustained thermal cycling and high pressures encountered in the aqueous homogenous reactor. Specialized stress-strain measurement techniques yielded information concerning flange deformation, ring type gask… more
Date: January 5, 1957
Creator: Fritz, K. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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