Resource Type
Collection
Serial/Series Title
Country
States
Counties
Month
744 Matching Results
Results open in a new window/tab.
Core Levitation in the EOCR in Case of Main Coolant Pipe Failure
This memorandum summarizes the results of an analysis to determine the extent of displacement of the EOCR core due to blowdown in case of several postulated hot main gas coolant pipe failures. Results show that the core will be damaged for any hot pipe double-ended failure. Excepting the improbable case of no coolant flow existing proper to the break, the core will be damaged for any hot pipe fracture exposing a total flow area to the atmosphere equal to that of one pipe. Smaller breaks will probably be safe in this respect.
Date:
August 4, 1959
Creator:
Fontana, M. H.
Object Type:
Report
System:
The UNT Digital Library
Calculation of Transport Cross Sections
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.
Object Type:
Report
System:
The UNT Digital Library
The Use of Boron for Fluoride Complexing in Thorex Dissolver Solutions
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.
Object Type:
Report
System:
The UNT Digital Library
Radiators for Space Power Plants
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 approach to the problem and a series of similar promising solutions.
Date:
August 7, 1959
Creator:
Fraas, A. P.
Object Type:
Report
System:
The UNT Digital Library
Molten-Salt Reactor Program Quarterly Progress Report: October 1959
Report documenting ongoing experiments, designs, and tests undertaken by the Oak Ridge National Laboratory for the Molten-Salt Reactor Project.
Date:
March 1, 1960
Creator:
MacPherson, H. G.
Object Type:
Report
System:
The UNT Digital Library
OR TEP: a FORTRAN Thermal-Ellipsoid Plot Program for Crystal Structure Illustrations
This report describes a computer program--Oak Ridge Thermal Ellipsoid Plot program (OR TEP)--for drawing crystal structure illustrations with a mechanical plotter.
Date:
June 1965
Creator:
Johnson, Carroll K.
Object Type:
Report
System:
The UNT Digital Library
Radiation Stability Studies
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.
Object Type:
Report
System:
The UNT Digital Library
Use of Steam-Electric Power Plants to Provide Thermal Energy to Urban Areas
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.
Object Type:
Report
System:
The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952
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.
Object Type:
Report
System:
The UNT Digital Library
Coupled Transmission Lines
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 more space is usually available. Tuning could be accomplished by variation of the coupling between the two circuits and/or by, say, variable capacitance of the tuned, or tunable, circuit.
Date:
June 1, 1959
Creator:
Worsham, R. E. & Mosko, S. W.
Object Type:
Report
System:
The UNT Digital Library
Calculations for Irradiation of Natural UO2-ThO2
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.
Object Type:
Report
System:
The UNT Digital Library
Containment Properties of DCX
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.
Object Type:
Report
System:
The UNT Digital Library
Methods of Controlling Core-Wall Temperatures in Aqueous Homogeneous Reactors
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.
Object Type:
Report
System:
The UNT Digital Library
ORIC R-F Model III Progress Report
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 measurements of the model characteristics.
Date:
June 2, 1959
Creator:
Worsham, R. E. & Mosko, S. W.
Object Type:
Report
System:
The UNT Digital Library
Nuclear and Economic Characteristics of several Two-Region Homogeneous Reactors
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.
Object Type:
Report
System:
The UNT Digital Library
Corrosion Status: Sulfex-Thorex (Ni-o-nel) and Darex-Thorex (Titanium) as of June 12, 1959
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.
Object Type:
Report
System:
The UNT Digital Library
Solids Accumulation and Fission Heating in the HRT Chemical Plant Underflow Pot (Co-op Report, Fall Quarter, 1958)
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 plant runs 17-4, 17-5, and 17-6. Further development work will be done on this correlation.
Date:
June 10, 1959
Creator:
Dunn, W. E.
Object Type:
Report
System:
The UNT Digital Library
Theoretical Study of Single-Transfer Line Concatenated Pulse Column Systems
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.
Object Type:
Report
System:
The UNT Digital Library
Uranium Anion Exchange Equilibria on Dowex 21K
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.
Object Type:
Report
System:
The UNT Digital Library
Estimate of Potential Fuel Reprocessing Revision #28 - Part A
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.
Object Type:
Report
System:
The UNT Digital Library
Unit Operations Section Monthly Progress Report June 1959
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 temperature of 1500°C.
Date:
September 4, 1959
Creator:
Bresee, J. C.; Haas, P. A.; Watson, C. D.; Whatley, M. E. & Horton, R. W.
Object Type:
Report
System:
The UNT Digital Library
Power Reactor Fuel Reprocessing Process Wastes
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.
Object Type:
Report
System:
The UNT Digital Library
A Comparison of Elementary Criticality Calculations with Experimental Results
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 less than unity' thus a higher critical concentration would be predicted than is actually observed.
Date:
June 11, 1959
Creator:
Nestor, C. W., Jr
Object Type:
Report
System:
The UNT Digital Library
A Review of the Mathematical Formulation of the Problem of Inelastic Neutron Scattering by Polycrystalline Material
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.
Object Type:
Report
System:
The UNT Digital Library