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Evaluation of Coolant Impurity Removal Equipment at the OMRE

Description: Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date: October 15, 1964
Creator: Barbour, P. & Davis, W. W.
Partner: UNT Libraries Government Documents Department

Heat Transfer Characteristics of Graphite Plates with Hydrogen Coolant

Description: "This note presents the results of a parametric study of heat-generating graphite plates with hydrogen coolant flowing through constant area passages. The heat generation within the graphite was assumed to have a distribution that allowed the centerline temperature of the plates to remain constant at 5000 F. The parametric variables were the mass flow rate per unit area, plate thickness, plate length, and passage hydraulic diameter. The machine calculations were coded by Ivan Cherry, T-1."
Date: October 19, 1955
Creator: Bussard, R. W. & Durham, F. P.
Partner: UNT Libraries Government Documents Department

Theoretical Study of Fission Product Gaseous Activity from a Homogeneous Reactor

Description: From abstract: Buildup of gaseous radioisotopes which are expected to be found in the atmosphere above a solution-fueled reactor has been calculated as a function of operating time. Krypton, iodine, xenon, and bromine have been considered. Direct fission and daughter yields are included in the summations of activities. Decay upon shutdown following various periods of equilibrium operation are tabulated.
Date: 1954
Creator: Donaldson, J. R.
Partner: UNT Libraries Government Documents Department

Fuel Elements Conference, Paris, November 18-23, 1957: Book 1, Sessions 1, 2, and 3

Description: Preface: The Fuel Elements Conference held in Paris, France, November 18 to 23, 1957, under the joint sponsorship of the U.S. Atomic Energy Commission and the French Commissarat à l'Energie Atomique (CEA), provided an intensive review of fuel-element fabrication practices and behavior of fuel elements under in-pile irradiation and when subjected to corrosive media.
Date: March 1958
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department

Supplement to Reactor Containment Design Study

Description: Summary: Report SL-1868 is a technical and economic feasibility study of four containment methods, i.e., standard containment, pressure relief, pressure supression and low pressure containment, for 44 MWe direct cycle and 180 and 300 MWe dual cycle boiling water reactor plants.
Date: April 23, 1962
Creator: Johnson, R. A. & Nelson, I.
Partner: UNT Libraries Government Documents Department

PM Research and Development Program: 1st Quarterly Progress Report, April 15, 1961 to June 30, 1961

Description: From summary: This report contains a description of the work accomplished during the first project quarter of the PM Research and Development Program, divided into six areas: core design development, plant design development, fuel element and core component development, critical experiments and zero power testing, reactor flow rates, and heat transfer tests.
Date: March 1962
Creator: Baer, R. L.
Partner: UNT Libraries Government Documents Department

High Temperature Heat Utilization in Industry

Description: Introduction: The United States Atomic energy Commission has guided the development of nuclear reactors for commercial applications for over a decade. the three most important development areas for industrial applications at the present time are for use in electric power generation, for productions of low temperature process steam, and for the supply of high temperature heat to manufacturing processes.
Date: April 1961
Creator: Ferguson, F. Alan; Towle, Leland H. & Tarrice, Richard R.
Partner: UNT Libraries Government Documents Department

Criticality in graphite systems

Description: From introduction: "The use of graphite in the collectors for the electromagnetic process results in the need for storage and processing of masses of U-235 contaminated carbons. Because of the widely differing moderating properties of carbon hydrogen, it was necessary to employ a modified thermal diffusion method to determine critical conditions, applicable to the Y-12 chemical cycle. It can be shown that the following treatment is basically the same as that used by X-10 in one-group pile calculations."
Date: 1947
Creator: Murray, Raymond & Schmidt, George W.
Partner: UNT Libraries Government Documents Department

Measurements of thermal distortion of the submarine intermediate reactor "Mark A" moderator tube

Description: Report presenting a moderator tube of the Submarine Intermediate Reactor (SIR) ("Mark A") subjected to temperature gradients considered to be representative of those occurring in the reactor during operation. The distortion of the tube was measured under two conditions: with the ends of the tube retained in the same manner at the reactor and with the ends of the tube simply supported.
Date: December 1952
Creator: Kemp, R. H. & Morgan, W. C.
Partner: UNT Libraries Government Documents Department