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Sodium Mass Transfer - I: Test Loop Design

Description: From abstract: "This report presents the design, fabrication, assembly, operating procedures, and start-up data for six experimental test loops to examine the effect of steel exposed to sodium at temperatures as high as 1300 F."
Date: June 1962
Creator: Lockhart, R. W.; Billuris, G. & Lane, M. R.
Partner: UNT Libraries Government Documents Department

Survey of Piping Failures for the Reactor Primary Coolant Pipe Rupture Study

Description: From summary: "An industrial piping failure survey covering 701 contacts in electric utilities, petroleum refineries, chemical processing, marine applications, architect-engineers, component manufacturers, piping fabricating and erectors, insurance companies, and others was conducted as part of the Reactor Primary Coolant Rupture Study."
Date: May 1964
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department

Prediction of the Critical Heat Flux in Forced Convection Flow

Description: From summary: "A superposition model is developed to predict the critical heat flux in forced convection flow. The model is applied to available experimental results in boiling water flows and good agreement is obtained between the model and test data over the multitude of geometries, flow rates, pressures, and fluid enthalpies tested to-date."
Date: June 20, 1962
Creator: Levy, S.
Partner: UNT Libraries Government Documents Department

Design Study: Sodium Modular Reactor

Description: This study was undertaken for the USAEC under Contract AT(04-3)-189, Project Agreement No. 6, to investigate desirable features of a sodium cooled, graphite moderated uranium fueled power reactor using the modular concept, and, based on this investigation, evaluate the economic potential of this reactor type.
Date: January 15, 1960
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department

Conceptual Design for 75 MWe Mixed Spectrum Superheating Reactor Power Plant

Description: "This report presents the conceptual design of a 75 MWe prototype Mixed Spectrum Superheater power plant. The scope of the work has emphasized primarily the design, performance, and cost information on the nuclear portion of the plant. The research and development programs required to insure plant feasibility are also present."--Intro.
Date: February 25, 1962
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department

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

VBWR Stability Test Report

Description: Analysis of the stability of boiling water reactors.
Date: June 1963
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department

Methods, System Optimization, and Safety Studies for a 1000 MegaWatt Sodium-Cooled Fast Reactor: Task 3 and 5 report of 1000 MegaWatt Liquid Metal Fast Breeder Reactor Follow-On Work

Description: From introduction: "Evaluation of trade-off and optimization studies in which numerous design parameters and economic ground-rules are varied to determine the effect on the economics of the reference concept. Selected safety studies."
Date: February 1969
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department

Simplified Power Conversion: Unit Study

Description: From abstract: "This report presents the results of a feasibility study on a simplified power conversion unit primarily for use with nuclear, steam power plants for military applications."
Date: June 1962
Creator: Clark, P. M.
Partner: UNT Libraries Government Documents Department

Multi-Rod Burnout at High Pressure

Description: From abstract: "Thirty-two burnout points were obtained on an electrically heated assembly of 9 simulated fuel rods in a square channel."
Date: September 1962
Creator: Polomik, E. E.
Partner: UNT Libraries Government Documents Department

Materials for Superheated Fuel Sheaths: Relative Performance of Alloys in Superheated Steam Environments

Description: From abstract: "Study of radiation effects upon the tensile properties of the alloys, corrosion behavior in the absence and presence of stress, effect of prolonged, high temperature exposures upon structure sensitive properties of the alloys, and physical metallurgical changes as a function of exposure in a superheat environment.
Date: July 1963
Creator: Comprelli, F. A.
Partner: UNT Libraries Government Documents Department

Steam-Cooled Power Reactor Evaluation: Mixed Spectrum Superheater

Description: From introduction: "This report provides the preliminary design for the nuclear portion of a 300 MWe Mixed Spectrum Superheater to be in operation by 1967.
Date: November 1960
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department

Design, Fabrication, and Irradiation of Superheat Fuel Element SH-4B in VBWR

Description: From abstract: "The design, fabrication, and irradiation results are described for a 0.028 inch thick 304 stainless clad fuel element (SH-4B) exposed in the Vallecitos Boiling Water Reactor loop under superheat conditions."
Date: September 1, 1961
Creator: Spalaris, C. N.; Boyle, R. F.; Evans, T. F. & Esch, E. L.
Partner: UNT Libraries Government Documents Department

1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3

Description: From introduction: "Contains the appendices and a complete set of drawings related to the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company for the United States Atomic Energy Commission."
Date: February 14, 1964
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department

Liquid Metal Fast Breeder Reactor Design Study: Volume 2

Description: From introduction: "Documentation of the various considerations and design techniques involved in the design of the reference 1000-MWe fast oxide breeder reactor."
Date: January 1964
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department