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The Fabrication of Thorium Tubes

Description: Abstract: "Thorium tubes were cold drawn from extruded tube stock and also from drilled hot-rolled rod. Total reductions up to approximately 85 per cent were accomplished by conventional tube-drawing methods, without an intermediate anneal. The hard-drawn tubes had high tensile strength, but the ductility, as indicated by flaring and flattening tests, was low."
Date: January 16, 1953
Creator: Saller, Henry A. & Keeler, J. R.
Partner: UNT Libraries Government Documents Department
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The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod

Description: Abstract: "Thirty-four uranium ingots containing controlled amounts of carbon, nitrogen, and Mgl2 slag were cast, rolled, and examined to investigate the relation between these impurities and the quality of the rolled rod. Carbon in concentrations up to 1400 ppm and nitrogen up to 170 ppm, either singly or in combination, had no significant effect on the number of defects observed in the rolled rod. The quality of the rods, however decreased with increasing amount of slag necessary to cause obs… more
Date: October 1, 1954
Creator: Saller, Henry A.; Keeler, J. R. & Cuddy, L. J.
Partner: UNT Libraries Government Documents Department
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Plastic Deformation in Grooved Rolls

Description: This report covers a study of the deformation characteristics of uranium in grooved rolls. The study's purpose was to provide a basis for possible improvements in the uniformity of the rolled rod produced for the Hanford and Savannah River reactors.
Date: September 27, 1955
Creator: Saller, Henry A.; Keeler, John R. & Cuddy, Lee J.
Partner: UNT Libraries Government Documents Department
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The Rolling of Thorium Rod

Description: Report discussing the rolling of thorium rods. Abstract: "Thorium rods, 1-7/16 inch in diameter, were rolled from Ames castings. The billets were roughed down in diamond-grooved rolls and finished in hand-rounding rolls. Remelted chips as well as primary-metal castings were rolled, and both yielded satisfactory rods. The surface quality of the rods was generally excellent, and the machined slugs were free of seams."
Date: December 19, 1951
Creator: Saller, Henry A.; Keeler, J. R. & Donley, R. J.
Partner: UNT Libraries Government Documents Department
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Experimental Fabrication of a Lightweight Control Rod

Description: Abstract: "The possibility of fabricating a lightweight control rod from one of several high cross-section materials was investigated. The major effort was directed toward the development of a titanium-clad rod containing a composite core of 25 weight per cent Gd2O3 in a matrix of titanium. Experimentation on both subscale and full-scale control-rod cores showed that the fabricating behavior of the two was not analogous. To roll the full-scale core successfully, it was necessary to lower the ox… more
Date: July 1, 1952
Creator: Saller, Henry A.; Stacy, J. T. & Keller, D. L.
Partner: UNT Libraries Government Documents Department
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The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod

Description: Abstract: "The effects of nitrogen, slag, and hydrogen additions on the surface quality of rolled uranium rod were studied. The addition of 400 ppm of nitrogen resulted in severe striations. Slag inclusions elongated during rolling and produced short open seams in the etched surface. The effects of 9 to 10 ppm of hydrogen were obscured by defects in the original costings. These defects were caused by oxide films entrapped in the ingot."
Date: 1956
Creator: Saller, Henry A.; Keeler, John R. & Cuddy, Lee J.
Partner: UNT Libraries Government Documents Department
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Solid-Phase-Reaction Studies of Control-Rod Materials

Description: Report discussing experiments on the interaction of neutron-absorber materials and metal matrix materials used in the fabrication of control rods, such as "boron, cadmium, and some of the rare-earth elements such as gadolinium and europium...In order to evaluate the reactions that might occur during fabrication and use, experiments were carried out in which combinations of the various control materials were heated in intimate contact with the several matrices at elevated temperatures."
Date: March 9, 1956
Creator: Gerds, Arnold F. & Mallett, Manley William, 1909-
Partner: UNT Libraries Government Documents Department
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Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies

Description: Report describing a pilot plant constructed at Argonne National Laboratory for studying two major process steps for the recovery of uranium and plutonium from spent nuclear fuels of power reactors. A major objective is the demonstration of optimum process conditions for the two steps for synthetic reactor fuel compositions, including those containing mixtures of inactive fission products.
Date: 1964
Creator: Vogel, G. J.; Carls, E. L. & Mecham, W. J.
Partner: UNT Libraries Government Documents Department
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Small Source Model of a Thermal Pile

Description: Report discussing the use of a small-source approximation for engineering calculation of thermal piles. Explanation for how this type of approximation is more appropriate in certain problematic situations where a homogenization approximation would be doubtful is given.
Date: April 30, 1952
Creator: Horning, W. A.
Partner: UNT Libraries Government Documents Department
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Reactor Physics of Teapot - Part 3

Description: Introduction: This is the third of a series of memoranda concerning the statics of the teapot, a small-scale boiling reactor experiment, and covers power coefficients of reactivity, energy coefficients of fluid density, the poisoning effects of fission products, and production of gases. The numbering of the equations, figures, and tables thus follows that of CF 52-6-118.
Date: July 16, 1952
Creator: Kasten, Paul R.
Partner: UNT Libraries Government Documents Department
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New Beta Heat-Treating Salt Baths for Reducing Hydrogen Pickup by Uranium Rods

Description: The following report summarizes the results of the laboratory-scale work and pilot-plant scale work of a salt-batch composition that reduces the hydrogen pickup by uranium rods during the beta heat treatment, and the study of the influence of humidity over the salt bath on hydrogen pickup.
Date: June 18, 1957
Creator: Lortscher, Lawrence L.; Sense, Karl A. & Filbert, Robert B., Jr.
Partner: UNT Libraries Government Documents Department
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Specification for Cleaning Zircaloy Fuel Rod Components

Description: Abstract: "This specification covers the cleaning of Zir caloy-2 components of PWR fuel rods and such tools, gauges, or other devices as may be required in subsequent handling, welding and inspection per Fuel Rod Specification AP-292545, Section II-A-4 and Section II-B-3."
Date: March 6, 1956
Creator: Fischer, R. L.
Partner: UNT Libraries Government Documents Department
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Silver - Cadmium - Indium Absorber Development

Description: Abstract: This technical report covers development of an AG-Cd-In alternate absorber section for Army Type SM reactors. It describes the absorber material composition and the geometric configuration. It gives the nuclear and thermal analyses supporting this configuration and a detailed description of the manufacturing practice employed in fabricating the final design component.
Date: June 13, 1962
Creator: Shaw, R. A. & Harris, R. L.
Partner: UNT Libraries Government Documents Department
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Theory of Asymmetric Arrays of Control Rods in Nuclear Reactors

Description: Introduction: Seldom does the actual arrangement of control elements in a nuclear reactor confers to the ideal and convenient mathematical array. In order to achieve shim control. safety and regulation, it is desirable to design with rods of different sizes and materials. With given fuel element arrangement, typically in square or hexagonal lattice spacing, there will be rods located at different distances form the center of the core and from each other. As the reactor operates, absorbers wil… more
Date: April 25, 1959
Creator: Murray, Raymond L.
Partner: UNT Libraries Government Documents Department
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SM-1 Reactor Core Inspection at 2/3 Core Life : March 7, 1959 to May 17, 1959

Description: Abstract: This technical report is concerned with the program and results of the SM-1 reactor vessel head removal and core inspection at Fort Belvoir, Virginia from the period March 7, 1969 to May 17, 1959. It covers the operating procedures in detail and records the conditions found and problems encountered in order to make a record for reference in future work of this nature. The major objective of the program, to obtain irradiation data on the SM-1 type core, has been met. The boron contro… more
Date: January 13, 1960
Creator: Obrist, C. H.; Byrne, B. J.; Connolly, T. F.; Foley, D. D.; Lichtenberger, R. V.; Mackay, S. D. et al.
Partner: UNT Libraries Government Documents Department
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DuPont Prototype Safety and Control Rod Drive Testing

Description: Summary: Prototype testing of the safety and control rod drives indicated that both units functioned properly. No major problems were encountered during testing. Seal leakage data collected indicated that the seal units were performing satisfactorily. Scram times during both cold and hot testing were excellent and actually better than expected.
Date: April 25, 1960
Creator: VandeMark, G. M. & Krause, P. S.
Partner: UNT Libraries Government Documents Department
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Fabrication of Fuel Rods by Tandem Rolling

Description: From introduction: "The purpose of this report is to present the details of the exploratory and developmental work on tandem rolling, and the subsequent fabrication of tandem rolled fuel rods for irradiation testing in the Vallecitos Boiling Water Reactor."
Date: July 1961
Creator: Lingafelter, J. W.
Partner: UNT Libraries Government Documents Department
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Environmental Testing of a B4C-Ni Prototype Control Rod

Description: Summary: A prototype control rod containing absorber plates made from an electro- deposited dispersion of boron carbide in nickel was tested in the VBWR. It was exposed to the reactor environment of 545 degree F boiling water and thermal neutron fluxes (perturbed) which ranged from 0.6 to 1.1 x 10/sup 13/ nv for 2236 hours over a period of six months. The maximum B/sup 10/ burnup achieved during the test period was 1.8 percent. After irradiation, the rod was examined. The results of the examina… more
Date: October 15, 1963
Creator: Megerth, F. H. & Zimmerman, D. L.
Partner: UNT Libraries Government Documents Department
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