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Analytical Studies of Transient Effect in Fast Reactor Fuels: [Part] 1

Description: From abstract: "An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined and possible mechanisms of failure are analyzed."
Date: August 1962
Creator: Osborn, R. B. & Sherer, D. B.
Partner: UNT Libraries Government Documents Department
open access

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
open access

Liquid Metal Fast Breeder Reactor Design Study: Volume 1

Description: From abstract: "A detailed description of a reference 1000-MWe fast breeder reactor plant is presented, together with design specifications and the experimental bases for the design."
Date: January 1964
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
open access

Comparison of Two Sodium-Cooled, 1000 MegaWatt Fast Reactor Concepts: Task 1 Report of 1000 MegaWatt Liquid Metal Fast Breeder Reactor Follow-On Work

Description: From introduction: "The development of one or more nuclear steam supply system concepts, with certain trade-off studies to aid in the definition of these concepts. The selection of a reference concept for further study."
Date: June 1968
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
open access

Experimental Studies of Transient Effects in Fast Reactor Fuels

Description: An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO₂ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F.… more
Date: November 15, 1962
Creator: Field, J. H.
Partner: UNT Libraries Government Documents Department
open access

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
open access

The Post-Irradiation Examination of a PuO₂-UO₂ Fast Reactor Fuel

Description: From abstract: "Post-irradiation examination consisted of dimensional measurements, gamma scans, determination of fission gas release, visual examination of the fuel, measurement central voids, and metallographic examination of selected samples.
Date: November 1961
Creator: Gerhart, J. M.
Partner: UNT Libraries Government Documents Department
open access

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
open access

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
open access

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
open access

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
open access

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
open access

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
open access

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
open access

1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2

Description: From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source."
Date: February 14, 1964
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
open access

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
open access

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. & Quinn, E. P.
Partner: UNT Libraries Government Documents Department
open access

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
open access

Fast Ceramic Reactor Development Program: Experimental Studies of Sodium Logging in Fast Ceramic Reactor Fuels

Description: From abstract: "The experimental determination of the effects of sodium ingress on high-performance oxide fuels is described. Capsule design, fabrication, irradiation, examination, and analysis are described in detail."
Date: September 1963
Creator: O'Neill, G. L.; Novak, P. E.; Johnson, M. L. & Baily, W. E.
Partner: UNT Libraries Government Documents Department
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