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Nuclear Superheat Quarterly Project Report: Thirteenth Quarter, July-September 1962

Description: From introduction: "This is the thirteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: May 15, 1963
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Fourth Quarterly Progress Report, January 1-March 31, 1963

Description: Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The experimental work centers around aspects of detecting neutrons in the presence of 10/sup 7/ r/hr gamma fields. Boric acid experiments and Humboldt Bay experiments are reported.
Date: May 13, 1963
Creator: Garelis, Edward & Meyer, Paul
Partner: UNT Libraries Government Documents Department
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Fuel Element Experiments in SADE-VBWR Nuclear Superheat Loop

Description: Abstract: Three irradiation experiments are described which have been designed to study the behavior of fuel elements in a reactors superheated steam environment. The experiments were conducted in the Superheat Advanced Demonstration Experiment loop, Vallecitos Boiling Water Reactor. The results obtained demonstrated that 304 stainless steel fuel clad in unsatisfactory for use in nuclear super heat fuel sheath designs where plastic strain or plastic deformation is allowed to occur. The resu… more
Date: May 1963
Creator: Spalaris, C. N.; Raymont, W. R.; Lyons, M. F.; Evans, T. F.; Boyle, R. F.; Murdock, T. B. et al.
Partner: UNT Libraries Government Documents Department
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Heat Transfer to Superheated Steam

Description: Abstract: The physical property variation of superheated steam differs sufficiently from most other gases to warrant experimental investigation of heat transfer performance. Results are reported here of measurements made in a uniformly heated circular duct with steam at 1000 psi. The data agree very well with the expression use for design purposes, which is based on information in the literature for heating of other gases as well as steam. This work was a continuation of that performed under … more
Date: May 1963
Creator: Sutherland, W. A. (William Alan), 1931-
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Project. Internal Steam Separation Development of Radial Vane Steam Separators

Description: This technical report describes the development, design, operation, and performance of a full-circle, radial-vane steam separator for the boiling water section of a nuclear superheat reactor. Steam-water tests of this model have demonstrated that is has vane capacity in excess of that required for the 300-Mx(e) separate superheat reactor and for the 300-Mw mixed spectrum superheat reactor. It is proposed that the vane capacity requirement of the 600 Mw(e) separate superheat reactor may be atta… more
Date: May 31, 1963
Creator: Moen, R. H.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Fifteenth Quarter, January-March 1963

Description: From introduction: "This is the fifteenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Date: May 15, 1963
Creator: Flock, W. L.
Partner: UNT Libraries Government Documents Department
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Homogeneous Circulating Fuel Reactor Power Plant: Conceptual Design Study Report

Description: The purpose of this report is to present a conceptual design study on a low power electrical and heat generating plant powered by nuclear energy. The nuclear reactor used in this study is the homogeneous circulating fuel type.
Date: May 31, 1955
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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Amendment No. 1 to Preliminary Hazards Summary Report For The Dresden Nuclear Power Station

Description: Commonwealth Edison Company for the purpose of supplementing the license application for the Dresden Nuclear Power Station submits herewith Amendment No.1 to the portion of the Final Hazards Summary Report entitled Preliminary Hazards Summary Report.
Date: May 26, 1958
Creator: Commonwealth Edison Company
Partner: UNT Libraries Government Documents Department
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The Rhode Island and Providence Plantations Atomic Energy Commission Nuclear Science Center Volume II - Safeguard Report

Description: This report presents the description and safeguard evaluation of an open pool research and test reactor rated at one megawatt. The reactor is being proposed by the General Electric Company to the Rhode Island and Providence Plantation Atomic Energy Commission.
Date: May 20, 1959
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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Physics Calculations for the Consumers Big Rock Point Process Computer

Description: The physics calculations to be performed on the Consumers On-Line Process Computer are reported. As a result of these calculations, a three-dimensional power shape is simulated, a reactivity balance is approximated, and the neutron exposure of each third of fuel bundle and control rod are accumulated. The work was reported as a part of the Consumers Research and Development Program.
Date: May 1963
Creator: Barth, N. H.
Partner: UNT Libraries Government Documents Department
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Application of Boron Carbide Nickel Dispersion to a Prototype Control Rod

Description: Previously reported results on the testing of small samples of boron carbide dispersed in nickel by electrolytic codeposition were adequately encouraging to lead to the development of a prototype control rod for operation in the Vallecitos Boiling Water Reactor. The operation of the control rod has been entirely satisfactory.
Date: May 1962
Creator: Williamson, H.E. & Alexander, A. J.
Partner: UNT Libraries Government Documents Department
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Economic Evaluation of Control Rod Materials and Fabrication Processes

Description: Control rod materials, designs, and fabrication processes are compared for their relative economies. Control rod lifetime data are calculated with a simple approximation of nuclear worth depreciation. These data are used in conjunction with the estimated fabrication costs to determine the cost of using several absorber materials in a typical power reactor on a cost-per-year basis. The effect the control system has on core power density and fuel lifetime is included.
Date: May 1962
Creator: Williamson, H. E. & Megerth, F. H.
Partner: UNT Libraries Government Documents Department
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