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Preliminary Evaluation of Licensing Issues Associated with U. S.-Sited CANDU-PHW Nuclear Power Plants

Description: The principal safety-related characteristics of current CANDU-PHW power plants are described, and a distinction between those characteristics which are intrinsic to the CANDU-PHW system and those that are not is presented. An outline is given of the main features of the Canadian safety and licensing approach. Differences between the U.S. and Canadian approach to safety and licensing are discussed. Some of the main results of the safety analyses, routinely performed for CANDU-PHW reactors, are p… more
Date: December 1977
Creator: van Erp, Jan B.
Partner: UNT Libraries Government Documents Department
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Occurrence of Critical Heat Flux During Blowdown with Flow Reversal

Description: A small-scale experiment using Freon-11 at 130 degrees F (54.4 degrees C) and 65 psia (0.45 MPa) in a well-instrumented, transparent annular test section was used to study the occurrence of critical heat flux (CHF) during blow-down with flow reversal. The inner stainless steel tube of the annulus was uniformly heated over its 61-cm length. Inlet and exit void fractions were measured by a capacitance technique. Flow-regime transition was observed with high-speed photography. A 1-hr contact time… more
Date: January 1977
Creator: Leung, J. C. M.
Partner: UNT Libraries Government Documents Department
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Formation and Quantification of Corrosion Deposits in the Power Industry

Description: The presence of deposits on the secondary side of pressurized water reactor (PWR) steam generator systems is one of the main contributors to the high maintenance costs of these generators. Formation and transport of corrosion products formed due to the presence of impurities, metals and metallic oxides in the secondary side of the steam generator units result in formation of deposits. This research deals with understanding the deposit formation and characterization of deposits by studying the s… more
Date: May 2007
Creator: Namduri, Haritha
Partner: UNT Libraries
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The Design Study of Fluid Engine Power Systems

Description: From abstract: This report presents information generated during a six month feasibility study of an engine which uses a supercritical working fluid as the secondary portion of nuclear powered electric generating system.
Date: April 12, 1963
Creator: Baker, C. H.; Hunter, T. A.; Pauliukonis, R. S. & Pradhan, A. V.
Partner: UNT Libraries Government Documents Department
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The Effects of Ternary Alloying Additions on the Corrosion Resistance of Epsilon-Phase Uranium-Zirconium Alloys

Description: Abstract: "The corrosion rate in 680 F water of the uranium-50 w/o zirconium binary alloy was found to be -0.20 mg/(cm2)(hr), and that of the uranium-40 w/o zirconium binary alloy was -0.34 mg/(cm2)(hr). Both alloys correlated uniformly, with no evidence of discontinuous failure. Normal variations in interstitial content in either alloy had no significant effect on corrosion behavior. Tantalum additions, in the range of 0.2 to 5 w/o, improved the corrosion rate of the uranium-50 w/o zirconium b… more
Date: April 27, 1956
Creator: Reynolds, James E.; Berry, Warren E., 1922-; Ogden, Horace R.; Peoples, Robert S. & Jaffee, Robert Isaac, 1917-
Partner: UNT Libraries Government Documents Department
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Effect of Ceramic or Metal Additives in High-UO₂ Bodies

Description: The following report focuses on research made to determine whether the service performance of UO₂ fuel-elements cores for the PWR can be improved by certain ceramic or metal additions.
Date: July 24, 1956
Creator: Bowers, Donald J.; Hedden, Walter A.; Snyder, M. Jack & Duckworth, Winston H.
Partner: UNT Libraries Government Documents Department
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Eddy-Current Inspection of a Possible PWR Fuel Element

Description: The following report follows the inspections of a number of eddy-current instrument procedures. The objectives of these tests were to detect both weld defects and lack of integrity of the body of the fuel elements.
Date: August 22, 1955
Creator: Stutz, David E.; Gibbs, Richard L.; Dickerson, Ronald F. & Wenk, Samuel A.
Partner: UNT Libraries Government Documents Department
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The Supercritical Water Reactor

Description: From summary: "During 1951 NDA has, at the request of ORNL, been studying the supercritical-water reactor as proposed for aircraft propulsion in Wash-24...This study has concerned itself only with the reactor and shield." The report describes the reactor and the processes involved in developing it. The goal of the development of this reactor is identified as a path to supersonic flight.
Date: January 2, 1952
Creator: Nuclear Development Associates, Inc.
Partner: UNT Libraries Government Documents Department
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Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report

Description: From preface: This report covers Phase I of the authorized work, consisting of determination of the specific reactor concept and size for the most economic reactor, preparation of a reference design of the most promising concept and estimated capital and generating costs, evaluation of the variations in cost as a function of unit size, and evaluation of the reductions in ultimate costs for a power station having multiple units of the same type.
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
Partner: UNT Libraries Government Documents Department
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Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant

Description: "This study is one of four initiated in 1958 by the Division of Reactor Development, U.S. Atomic Energy Commission, to assess the feasibility of power generation through the use of certain types of nuclear reactors. These studies are available from the Office of Technical Services, U.S. Department of Commerce, Washington 25, D.C."
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
Partner: UNT Libraries Government Documents Department
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Carolinas Virginia Tube Reactor: Large Plant Study

Description: From introduction: The Carolinas Virginia Tube Reactor is to be designed as a prototype for a large-scale plant of about 200 megawatts electrical or larger, wherein operation with natural uranium feed material may be feasible but such feed material can only be considered if it is the more economical.
Date: June 1963
Creator: Westinghouse Electric Corporation. Atomic Power Division.
Partner: UNT Libraries Government Documents Department

Characterization of Iron Oxide Deposits Formed at Comanche Peak Steam Electric Station

Description: The presence of deposits leading to corrosion of the steam generator (SG) systems is a major contributor to operation and maintenance cost of pressurized water reactor (PWR) plants. Formation and transport of corrosion products formed due to the presence of impurities, metallic oxides and cations in the secondary side of the SG units result in formation of deposits. This research deals with the characterization of deposit samples collected from the two SG units (unit 1 and unit 2) at Comanche P… more
Access: Restricted to the UNT Community Members at a UNT Libraries Location.
Date: May 2003
Creator: Namduri, Haritha
Partner: UNT Libraries
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Flow Accelerated Corrosion Experience at Comanche Peak Steam Electric Station

Description: Flow accelerated corrosion (FAC) is a major concern in the power industry as it causes thinning of the pipes by the dissolution of the passive oxide layer formed on the pipe surface. Present research deals with comparing the protection offered by the magnetite (Fe3O4) versus maghemite (γ-Fe2O3) phases thickness loss measurements. Fourier transform infrared spectroscopy (FTIR) is used in distinguishing these two elusive phases of iron oxides. Representative pipes are collected from high pressure… more
Date: May 2008
Creator: Nakka, Ravi Kumar
Partner: UNT Libraries
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Army PWR Support and Development Program Six Months Summary Report : October 1, 1961 - March 31, 1962

Description: Abstract: Progress is reported on research and development tasks under the Program Plan for Engineering Support and Development of Army Pressurized Water Reactor Power Plants, Contract AT(30-1)-2639, during the six months' period October 1, 1061 to March 31, 1962.
Date: May 25, 1962
Creator: Dixon, M. H.
Partner: UNT Libraries Government Documents Department
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Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat

Description: Report describing the development, fabrication, and nondestructive and destructive evaluation of stainless steel-clad fuel plates, the evaluation of fuel subassemblies, and the assembly of fuel element components at Argonne National Laboratory.
Date: December 1963
Creator: Kramer, W. C. & Bean, C. H.
Partner: UNT Libraries Government Documents Department
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In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962

Description: Report containing the results of a two year program wherein the 85 zircaloy-2 pressure tubes in Hanford Laboratories' Plutonium Recycle Test Reactor (PRTR) were monitored. Experimental procedures and results are described.
Date: August 1962
Creator: Doman, D. R. & Pankaskie, P. J.
Partner: UNT Libraries Government Documents Department
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