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A Parametric Study of a Gas Cooled Reactor

Description: The results of a parametric study on a gas cooled reactor are reported on herein. The system considered was a helium cooled, UO2 fueled arrangement with the fuel assemblies consisting of clusters of long cylindrical elements, each element covered b a stainless steel jacket. The axial power distribution was assumed to be a "chopped cosine" having an axial peak-to-average power 1.32.
Date: July 24, 1959
Creator: Epel, L. G.
Partner: UNT Libraries Government Documents Department
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Lecture Notes on Reactor Controls

Description: This course on reactor controls is for the purpose of acquainting the student with some of the elementary considerations involved in setting up a control and safety system for a nuclear reactor. This material is the outgrowth of the notes prepared for the lectures on Reactor Controls given in the Oak Ridge School of Reactor Technologu. The lectures given by T. E. Cole in 1953-1955 are the basis of portions of the subject matter on reactor kinetics. Many suggestions and ideas contributed by E. R… more
Date: June 24, 1959
Creator: Walker, C. S.
Partner: UNT Libraries Government Documents Department
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The Equation of the Fusion Curve

Description: A generalization of the Lindemann law is used in connection with the Murnaghan equation of state for a solid to derive theoretically the empirical Simon equation for the fusion curve. For the alkali metals it is shown that experimental values of the temperature exponent in the Simon equation are quantitatively compatible with the theoretical evaluation given, and, furthermore, that the theory can predict approximate values of the experiment, in practice.
Date: May 24, 1955
Creator: Gilvarry, J. J. (John James), 1917-
Partner: UNT Libraries Government Documents Department
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Fundamentals of Glass-to-Metal Bonding. [Part] 5-A. Temperature and Pressure Dependence of the Wettability of Metals by Glass. [Part] 5-B. Reactions of Tantalum and sodium Silicate Glass. Technical Report No. 5

Description: Part A. The major effort during the past year has been the construction of a suitable vacuum furnace for studying the effects of temperature and pressure on the wettability of metals by glass. A systems was completed that was capable of subjecting test combinations up to temperatures of 1400 degree C at a working pressure of 1 x 10(-5) mm. of Hg. Part B. A compound, identified by X-ray analysis as sodium meta tantalate (na2Ta2O6), was found at the interface between a sodium silicate glass and t… more
Date: June 24, 1955
Creator: Fulrath, Richard M.; Mitoff, Stephan P. & Pask, Joseph A. (Joseph Adam), 1913-2003.
Partner: UNT Libraries Government Documents Department
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Zirconium Alloys for Steam Service: a Preliminary Study

Description: The fabricability, elevated temperature strength, steam corrosion resistance, and hydrogen pickup of various binary, ternary, and quaternary alloys were studied experimentally.
Date: June 24, 1960
Creator: Klepfer, H. H.
Partner: UNT Libraries Government Documents Department
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Enclosure Section of the Hazards Summary Report for the Dresden Nuclear Power Station

Description: The General Electric Company is designing and building a 180,000 kilowatt nuclear power plant for the Commonwealth Edison Company at a site near the confluence of the Kankakee and Des Plaines Rivers in Grundy County, Illinois, about 47 miles southwest of Chicago. The plant will be known as the Dresden Nuclear Power Station, and will employ a nuclear reactor of the dual-cycle boiling water type.
Date: January 24, 1957
Creator: Commonwealth Edison Company
Partner: UNT Libraries Government Documents Department
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High-Thermal-Conductivity Fin Material for Radiators

Description: This report is the result of a study to develop heat-resistant fin materials possessing a high thermal conductivity for air radiators. Since an economical and commercially feasible product was desired, the investigation was restricted primarily to a study of electroplated copper, clad copper, and copper alloys. Sheet material 0.008 to 0.010 in. thick was evaluated for fabricability and for metallurgical stability and thermal conductivity at 1500°F. From the results of the rests it was concluded… more
Date: January 24, 1957
Creator: Inouye, H.
Partner: UNT Libraries Government Documents Department
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Thorex Thorium Nitrate Product Specifications

Description: Activity and ionic impurity specifications are presented for Thorex thorium nitrate products. Two sets of specifications are given, one set for direct handling during refabrication of production reactor thorium metal slugs and the second for refabrication of future power reactor thorium metal elements by semi-remote technics. Consideration was given to the health hazard problems associated with each process step between the Thorex process and final refabricated source material in order to arriv… more
Date: May 24, 1956
Creator: Arnold, E. D. & Wischow, R. P.
Partner: UNT Libraries Government Documents Department
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Bulk ThO2, a Reactor Material

Description: Thorium, a fertile material, is of interest to the Reactor Program in the production of U233. Thorium can be extracted and processed to a very pure bulk metal for fabrication into solid fertile elements. There are advantages, technical and economic, for using fabricated bulk thorium dioxide rather than the metal in some applications. It is the purpose of this paper to point out these advantages and to present briefly the technology related to fabrication, radiation damage and chemical processin… more
Date: May 24, 1956
Creator: Johnson, J. R. & Warde, J. M.
Partner: UNT Libraries Government Documents Department
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Determination of Corrosion Products and Additives in Homogeneous Reactor Fuel III. Polarographic Determination of Iron(III)

Description: An ion-exchange -- polarographic method was developed for the determination of iron(III) in Homogeneous Reactor Fuels. Copper, which interferes, is removed from the fuel by plating it onto a cadmium coil. Iron is oxidized to iron(III) by potassium permanganate, and the iron(III) is separated from interfering metal ions by ion exchange on a Dowex 1 resin column that is in the sulfate form. The iron(III) in the effluent is determined polarographically in 0.5 M sodium citrate solution as supportin… more
Date: October 24, 1955
Creator: Horton, A. D.; Thomason, P. F. & Raaen, H. P.
Partner: UNT Libraries Government Documents Department
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Electronuclear Research Division Semiannual Progress Report For Period Ending March 20, 1955

Description: The ORNL 86-in. cyclotron is being modified to provide for deflection of the proton beam. It is expected that operation will be resumed late in the spring. Nuclear physics work was limited, for the most part, to interpretation of previously collected data and to making preparations for utilizing the deflected beam. It was found that for certain isotopes the production rates could be almost doubled by operating at a slightly reduced energy and a much larger current. With the use of the ORNL 63-i… more
Date: June 24, 1955
Creator: Livingston, Robert S. & Howard, F. T.
Partner: UNT Libraries Government Documents Department
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Termination Report for Development Test IP-306-K Spline Coilers at K Reactor

Description: A reliable spline disposal system is necessary for full utilization of the Poison Spline Control System. The spline choppers were not reliable enough so a spline coiler was developed and designed to replace the choppers. A Development Test, IP-306-X (HW-63820), was issued authorizing on-pile testing of the spline coiler at X area. This report closes the Development Test and discusses the use of spline coilers.
Date: June 24, 1960
Creator: McCarthy, P. B.
Partner: UNT Libraries Government Documents Department
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Nuclearly Safe Mass Limits, Volume Limits, Infinite Cylinder Diameters and Slab Thicknesses for Slightly Enriched Uranium Rods in Light Water

Description: Graphs have been made which show the nuclearly safe parameters for uranium rods in light water with uranium enrichments up to five weight percent U-235. These data were to serve as a guide to those persons who may be involved with the maintenance of nuclear safety in handling and processing operations with slightly enriched uranium fuel elements. The data are applicable to fuel element fabrication and processing operations, and in general to those operations involving the handling and storage o… more
Date: May 24, 1960
Creator: Clayton, E.D.
Partner: UNT Libraries Government Documents Department
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Preliminary Report on the Use of Activated Carbon as a Catalyst for the Dissolved Oxygen-Aqueous Hydrazine Reaction

Description: Theoretically aqueous hydrazine will react with dissolved oxygen for form only nitrogen and water. Most of the experimental evidence, however, indicates that the reaction proceeds rather slowly in low-temperature systems. Tests are currently being conducted to determine whether or not it is feasible to use activated carbon to catalyze the reaction in filtered water. A system of this type would be useful in high temperature reactors when it becomes necessary to convert to single-pass operation.
Date: February 24, 1960
Creator: Demmit, T. F.
Partner: UNT Libraries Government Documents Department
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Development and Testing of an Improved Agitator for the Redox and Purex Separations Plants

Description: Relatively frequent agitator failures in HAPO Separations Plants have interfered with process continuity, contributed to process difficulties, and resulted in considerable maintenance expense. Predominantly the failures have been because of gear-reduction drive unit break-down or because of metallic fatigue and degeneration of the shaft-paddle assemblies. A simplified, slow-speed, direct drive agitator, previously described in HW-52755, proved to be quite durable and satisfactory during extende… more
Date: December 24, 1959
Creator: Dunn, J. & Sloat, R. J.
Partner: UNT Libraries Government Documents Department
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The Nuclear Reactor with a Transverse Air Gap

Description: Diffusion theory and transport theory approaches to the problem of a nuclear reactor with a transverse air gap are compared. It is suggested that the differences in results for thin gaps is due to the fact that diffusion theory does not adequately represent the flux distribution in the immediate vicinity of the gap. For mathematical conveniences previous treatments of the gap problem have made use of fictitious image piles which exaggerate the neutron losses. The extent of the error is estimate… more
Date: August 24, 1954
Creator: Chernick, J. & Kaplan, I.
Partner: UNT Libraries Government Documents Department
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The Role of Internal Conversion in the Study of Isomeric Transitions

Description: A short review of the field of internal conversions. Isomeric transitions teach us many details of nuclear structure. In these studies electromagnetic theory is considered as a "tool". It is a quite quantitative tool in the case of "internal conversion" - a phenomenon which has been widely studied for many years. Internal conversion takes place in competition with γ-ray emission: a fraction of the nuclei in excited states decay by γ-ray emission, the remaining fraction by transferring the energ… more
Date: June 24, 1954
Creator: Goldhaber, M.
Partner: UNT Libraries Government Documents Department
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The Cosmotron Radio Frequency Accelerating System

Description: The proton beam in the Cosmotron is accelerated to an energy of 2.3 billion electron volts by a radio frequency voltage which is impressed across an insulated gap in the ferrite loaded accelerating cavity of the vacuum chamber. To maintain a constant orbit radius as the beam is accelerated, the frequency of the accelerating voltage must increase from the initial value of 370 kc/sec to 4200 kc/sec during the one second magnet pulse. Over the entire 11:1 frequency range, a minimum gap voltage of … more
Date: November 24, 1953
Creator: Rogers, Edwin, J. & Flotkin, M.
Partner: UNT Libraries Government Documents Department
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Calculation of Average Flux in Moderator of Water Lattices by Means of a Relaxation Method

Description: The following report concerns the application of a relaxation mesh method for the determination of the average flux within the moderator of a light water moderated, 1.027 per cent U-235, hexagonal lattice with a volume ratio (V_H2O + V_Al)/V_Uranium of 4:1. It was hoped that the calculation would enable one to determine any differences in flux which might result from the fact that the unit cell is a hexagon instead of a cylinder. Because we were primarily interested in the effect due to geometr… more
Date: March 24, 1953
Creator: Oleksa, S. & Mozer, B.
Partner: UNT Libraries Government Documents Department
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Eurochemic Questions -- Preliminary Report

Description: The referenced memo asked several questions on the operation of the Purex Plant which are of interest to the Eurochemic personnel. These questions are answered below. 1. A qualitative description of the nitric acid recovery systems is desired -- flow of materials, number of pieces of equipment, etc.
Date: August 24, 1959
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
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Eddy Current Ultrasonic Transducer

Description: In the field of nondestructive testing the ultrasonic test method is used extensively. In this method ultrasonic energy generated by a transducer is caused to enter the test specimen. The effect on the transducer is cause to enter the test specimen. The effect on the transmission or reflection of the ultrasonic energy by differing test specimen structure is used as an indirect measure of test specimen characteristics.
Date: August 24, 1959
Creator: Libby, Hugo L.
Partner: UNT Libraries Government Documents Department
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Analysis of a Nuclear Incident in a Redox Dissolver

Description: Since the start of E-metal processing in December, 1958, critical mass control in the Redox dissolvers has been provided by a combination of administrative controls, revised dissolver charging procedures, and new dissolving processes and operation control procedures. These were all based on a maximum allowable charge of E-Metal to the dissolvers which was equivalent to 45 percent of the minimum critical mass.
Date: August 24, 1959
Creator: Neely, V. I.
Partner: UNT Libraries Government Documents Department
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DC Bridge NPR Horizontal Rod Counting

Description: This report is a summary of work done for system development on the NPR ball safety backup for the horizontal rods. This phase of the system development is limited to discussion of the horizontal rod counting circuitry utilizing a direct current bridge network.
Date: July 24, 1959
Creator: {{{name}}}
Partner: UNT Libraries Government Documents Department
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