Technical Report Archive & Image Library (TRAIL) - 32 Matching Results

Search Results

Results: 1 - 32
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
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."
Comparison of Two Sodium-Cooled, 1000 MegaWatt Fast Reactor Concepts: Task 1 Report of 1000 MegaWatt Liquid Metal Fast Breeder Reactor Follow-On Work
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."
Survey of Piping Failures for the Reactor Primary Coolant Pipe Rupture Study
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."
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1
From introduction: "Summary report of the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company."
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2
From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source."
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3
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."
Liquid Metal Fast Breeder Reactor Design Study: Volume 1
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."
Liquid Metal Fast Breeder Reactor Design Study: Volume 2
From introduction: "Documentation of the various considerations and design techniques involved in the design of the reference 1000-MWe fast oxide breeder reactor."
A Survey of Water Reactor Primary System Conditions Pertinent to the Study of Pipe Rupture
"Designers, builders and operators of water cooled reactor systems have been queried regarding the range of parameters which should be investigated in a study of piping rupture."
Analysis of Failure of Type 304 Stainless Steel Clad Swaged Powder Fuel Assembly
From introduction: "The purpose of this report is to describe the observations made during the post-irradiation examination of HPD-2S, and to discuss possible modes of failure.
Fast Ceramic Reactor Development Program: Experimental Studies of Sodium Logging in Fast Ceramic Reactor Fuels
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."
Materials for Superheated Fuel Sheaths: Relative Performance of Alloys in Superheated Steam Environments
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.
VBWR Stability Test Report
Analysis of the stability of boiling water reactors.
Evaluation of Failed Hot Gas Isostatic Pressed Fuel Rods
From introduction: "Evaluations to determine cause of fuel rods breakage following irradiation."
Comparative Study of PuC-UC and PuO₂-UO₂ as Fast Reactor Fuel
From abstract: "This section, Part II, extends the comparison of two ceramic fuel systems to include the fuel cycle cost comparison in greater detail particularly with respect to fabrication and reprocessing unit costs."
Experimental Studies of Transient Effects in Fast Reactor Fuels
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. Multiple transient damage to the cladding is likely for transients above the melting point of the fuel.
Design Study of a 600 MWe Boiling Water - Separate Superheat Reactor Plant
From introduction: "This report provides a final design and cost estimate for a 607 MWe Boiling Water - Separate Superheat Reactor Plant."
Multi-Rod Burnout at High Pressure
From abstract: "Thirty-two burnout points were obtained on an electrically heated assembly of 9 simulated fuel rods in a square channel."
Analytical Studies of Transient Effect in Fast Reactor Fuels: [Part] 1
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."
Prediction of the Critical Heat Flux in Forced Convection Flow
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."
Simplified Power Conversion: Unit Study
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."
Sodium Mass Transfer - I: Test Loop Design
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."
Conceptual Design for 75 MWe Mixed Spectrum Superheating Reactor Power Plant
"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.
Results of Air-Water and Steam-Water Tests on Radial Vane Steam Separator Models
From introduction: "Describes progress in the development of radial vane primary separators following initial work reported in GEAP 3564."
High Power Density Development Project: Interim Report, 300 MWe HPD Conceptual Design Study
From introduction: "Preliminary design and analysis of the 300 MWe core."
The Post-Irradiation Examination of a PuO₂-UO₂ Fast Reactor Fuel
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.
Design, Fabrication, and Irradiation of Superheat Fuel Element SH-4B in VBWR
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."
Fabrication of Fuel Rods by Tandem Rolling
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."
Heat Transfer Coefficients with Annular Flow During "One-Through" Boiling Water to 100 Per Cent Quality at 800, 1100, 1400 PSI
From introduction: "Once-Through boiling of water to 100 per cent steam quality was successfully accomplished. Results of Departure from Nucleate Boiling, transition, and film boiling tests are presented."
Steam-Cooled Power Reactor Evaluation: Study of 300 Mw(e) Once-Through Superheater Reactor
From introduction: "This report presents a conceptual design study of the once-through superheat reactor design based on experimental heat transfer results obtained during the fall of 1960 on Task F-2 of the AEC sponsored Nuclear Superheat Project."
Steam-Cooled Power Reactor Evaluation: Mixed Spectrum Superheater
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.
Design Study: Sodium Modular Reactor
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.
Back to Top of Screen