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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.
Partner: UNT Libraries Government Documents Department
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The Use of Boron for Fluoride Complexing in Thorex Dissolver Solutions

Description: Preliminary measurements of the corrosion of titanium were made in 13 M HNO3-0.05 M fluoride using 0.1 M H3BO3 as a liquid and vapor phase complexing agent. Titanium Ax-55 was attacked at average rates of 0.58 and 0.33 mils/month in the liquid and vapor. In dissolver solutions containing 0.5 and 1.0 M titanium, all rates were less than 0.1 mils/month.
Date: August 6, 1959
Creator: Kitts, F. G.
Partner: UNT Libraries Government Documents Department
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Radiators for Space Power Plants

Description: An improved heat sink for space vehicles was proposed in ORNL-CF-59-1-21. Subsequent work on the problem has indicated that there is a substantial probability of a puncture of such a radiator by meteors. To meet this problem a modified geometry has been evolved for which the probability of a meteor puncture should be reduced by a factor of at least 100 relative to the radiator of the original proposal at the expense of an increase in radiator weight of possibly 30%. This memorandum outlines the… more
Date: August 7, 1959
Creator: Fraas, A. P.
Partner: UNT Libraries Government Documents Department
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Radiation Stability Studies

Description: From abstract: "An investigation of the radiation stabilities of aqueous solutions of sodium ethylenediamine tetraacetate and sodium acetate was made using a 3000-curie Co⁶⁰ source...A study of the behavior of the standard-size Beckman type glass pH electrodes in a solution containing 0.36 curie of Ce¹⁴⁴-Pr¹⁴⁴ activity per milliliter showed the useful electrode life to be of the order of two to eight days."
Date: September 22, 1952
Creator: Blanco, R. E.; Kibbey, A. H. & Pannell, J. H.
Partner: UNT Libraries Government Documents Department
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Use of Steam-Electric Power Plants to Provide Thermal Energy to Urban Areas

Description: This report presents the results of a study that argues the importance of providing thermal energy from steam-electric power plants to urban areas.
Date: January 1971
Creator: Miller, A. J.; Payne, H. R.; Lackey, M. E.; Samuels, G.; Heath, M. T.; Hagen, E. W. et al.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952

Description: This quarterly progress details ongoing research at the Oak Ridge National Laboratory as a part of the Aircraft Nuclear Propulsion Project. Topics discussed include reactor theory and design, [part two is not included], materials research, and appendixes with information on analytical chemical studies.
Date: October 23, 1952
Creator: Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, William B.
Partner: UNT Libraries Government Documents Department
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Coupled Transmission Lines

Description: In a discussion about design of cyclotron resonators, the suggestion has been made that a wide range variable-frequency system might be constructed with two coupled resonant circuits. It also would present the possibility of tuning without the switching of high-current contacts, a troublesome item now commonly used for cyclotrons. One of the circuits would be the dee and its stem which might, or might not, be tuned. The second circuit could be located out of the magnet gap in a region where mo… more
Date: June 1, 1959
Creator: Worsham, R. E. & Mosko, S. W.
Partner: UNT Libraries Government Documents Department
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Calculations for Irradiation of Natural UO2-ThO2

Description: Calculations are given for eighteen stainless steel clad helium bonded specimens of UO2-ThO2 containing normal U to be placed in 6 holes in a holder in a position of the ORR not to exceed a peak unperturbed flux of 4 x 10^14 n.cm^2/sec and irradiated to a peak nvt of 1.96 x 10^21 neutrons/cm^2
Date: June 8, 1959
Creator: Ullmann, J. W.
Partner: UNT Libraries Government Documents Department
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Containment Properties of DCX

Description: The "absolute" containment of ions in the DCX magnetic mirror field resulting from the cylindrical symmetry of the field is discussed. The regions of confinement in space and momentum are plotted for 300 Kev deuterons.
Date: June 15, 1959
Creator: Fowler, T. K. & Rankin, M.
Partner: UNT Libraries Government Documents Department
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Methods of Controlling Core-Wall Temperatures in Aqueous Homogeneous Reactors

Description: The problem of controlling the surface temperatures of core vessels in two-region aqueous homogeneous reactors has been examined by analyzing several possible systems for cooling the wall: (1) direction of the inlet core fluid along the wall at a high velocity; (2) passage of heavy water through the wall of a double-wall core vessel; and (3) flow of cool blanket slurry past the wall.
Date: June 3, 1959
Creator: Rosenthal, M. W.
Partner: UNT Libraries Government Documents Department
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ORIC R-F Model III Progress Report

Description: The ORIC (Oak Ridge Relativistic Isochronous Cyclotron) radiofrequency system for which Model III represents the resonator is the third system which has received enough consideration to warrant construction of a model. The purpose of the model is to check the calculations for the frequency range and excitation power of the resonator. After an introductory description of the r-f system and model, the detailed calculations of the properties of the model will be given followed by the data from me… more
Date: June 2, 1959
Creator: Worsham, R. E. & Mosko, S. W.
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.
Partner: UNT Libraries Government Documents Department
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Corrosion Status: Sulfex-Thorex (Ni-o-nel) and Darex-Thorex (Titanium) as of June 12, 1959

Description: Either system appears to be fairly satisfactory from a containment standpoint. Current results indicate probable over-all rates of about 0.2mils/mo for titanium vs. 1.5-3.0 mils/mo for Ni-o-nel. Tests are not 100% comparable due to changes made in flowsheet conditions, but have been of sufficient variation and length as to allow good predictions to be made. Both metals show some tendency toward local attack in Thorex solutions. These tendencies are increased by poor welding techniques.
Date: June 29, 1959
Creator: Clark, W. E.
Partner: UNT Libraries Government Documents Department
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Solids Accumulation and Fission Heating in the HRT Chemical Plant Underflow Pot (Co-op Report, Fall Quarter, 1958)

Description: The purpose of this study was to develop equations for calculating fision product heating in the HRT-CP underflow pot from measured temperatures and to attempt to correlate the rat of solids accumulation in the underflow pot with fission heating and reactor power. Using fission heating data calculated from relating solids accumulation and heating have been tested. In one case an error of no greater than 26% was incurred in the calculation of the total weight of solids collected during chemical … more
Date: June 10, 1959
Creator: Dunn, W. E.
Partner: UNT Libraries Government Documents Department
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Theoretical Study of Single-Transfer Line Concatenated Pulse Column Systems

Description: Calculations indicate that single-transfer line concatenated pulse column systems can be operated with static pressures that are not excessive if a sufficient number of vessels are employed in the system. The required number of vessels can be attained by using a series of short columns or by using holdup pots in conjunction with a limited number of columns.
Date: June 19, 1959
Creator: Johnson, H. F.
Partner: UNT Libraries Government Documents Department
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Uranium Anion Exchange Equilibria on Dowex 21K

Description: Equilibrium loading of uranium on Dowex 21K has been studied in a sulfate system for uranium concentrations from 0.0005 M to 0.0005 M, total sulfate concentrations of 0.45 M to 0.6M, and sulfuric acid concentration of 0.020 M. Loading data have been fitted to Langmuir adsorption isotherms and Langmuir constants have been evaluated. Resin was equilibrated with uranium feed solutions by flowing the feed through a shallow fixed bed of resin.
Date: June 29, 1959
Creator: Dunn, W. E.
Partner: UNT Libraries Government Documents Department
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Estimate of Potential Fuel Reprocessing Revision #28 - Part A

Description: The power and estimated reprocessing load are tabulated for existing and proposed United States and United States-built reactors of 10 Kw or greater thermal power.
Date: June 25, 1959
Creator: Ullmann, J. W.
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report June 1959

Description: The addition of a surface active agent to an aqeous-organic interface produced a resistance to mass transfer equivalent to slightly more than 1 cm of water. Five semicontinuous Druhm runs were made with 1/2in. thick MgO liners and terminated due to either failures of the UFe nozzle or a top gasket leak. In preliminary scale-up tests of the flame calcination equipment, a maximum feed rate equivalent to 720 g oxides/hr was achieved using a 3-in. i.d. magnesia reflector with an outside wall temper… more
Date: September 4, 1959
Creator: Bresee, J. C.; Haas, P. A.; Watson, C. D.; Whatley, M. E. & Horton, R. W.
Partner: UNT Libraries Government Documents Department
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Power Reactor Fuel Reprocessing Process Wastes

Description: Data on waste volumes and heat generation of several reactor fuels which may be reprocessed in the Power Reactor Fuel Reprocessing Pilot Plant at ORNL are tabulated.
Date: June 19, 1959
Creator: Irvine, A. R.
Partner: UNT Libraries Government Documents Department
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A Comparison of Elementary Criticality Calculations with Experimental Results

Description: Several experiments have been performed at ORNL with light water solutions of uranyl nitrate (highly enriched in either U^233 or U^235) in an essentially bare sphere 27 inches in diameter. This report presents the results of several calculations with elementary bare reactor theory and a discussion of the observed discrepancies between the calculated and experimental results. If the observed critical concentration is used in the calculations, the calculated effective multiplication constant is l… more
Date: June 11, 1959
Creator: Nestor, C. W., Jr
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.
Partner: UNT Libraries Government Documents Department
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Radiation Hazards from Recycled Reactor Fuel

Description: The radiation hazards associated with recycled nuclear reactor fuels will greatly complicate the handling and refabrication of these fuels. This problem is most serious with U-233 and plutonium fuels where the presence of U-232 and the heavier isotopes of plutonium contribute energetic alpha, gamma, and neutron radiations at levels many times that from isotopically pure U-233 and Pu-239. This report summarizes present knowledge of the radiation hazards associated with recycled fuel and the addi… more
Date: June 9, 1959
Creator: Arnold, E. D.
Partner: UNT Libraries Government Documents Department
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