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30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures
Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
Washing of brine from ice crystals
No Description Available.
Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor
Report that describes the Oak Ridge National Laboratory Experimental Gas-Cooled Reactor, problems with the procurement and assembly of its components, and its economic feasibility.
Saturated Liquid Densities of Oxygen, Nitrogen, Argon, and Parahydrogen
Integrated tables of pressure, volume, and temperature for the saturated liquid, from the triple point to the critical point, for oxygen, nitrogen, argon, and parahydrogen.
Temperature-Entropy Diagram for Parahydrogen Triple-Point Region
Graphical presentation of he three-phase region at and near the triple point of parahydrogen.
Calculation of Sunrise and Sunset Times at Ionospheric Heights Along a Great Circle Path
Formulas, computer program, and illustrations for a great circle path at ionospheric heights.
Nuclear Superheat Quarterly Project Report: Eighth Quarter, April-June 1961
From introduction: "This is the eighth of 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."
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."
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."
Nuclear Superheat Quarterly Project Report: Seventh Quarter, January-March 1961
From introduction: "This is the seventh of 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."
Nuclear Superheat Quarterly Project Report: Ninth Quarter, July-September 1961
From introduction: "This is the ninth of 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."
Nuclear Superheat Quarterly Project Report: Thirteenth Quarter, July-September 1962
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."
HAYSTAQ: a Mechanized System for Searching Chemical Information
Description of a computer program for searching chemical information on magnetic tape.
One-Pion Exchange and the Optical Model
A report on one-pion exchange and the optical model.
A Comparison of Two Melting-Pressure Equations Constrained to Triple Point Using Data for Eleven Gases and Three Metals
Parameters determined by a least-squares method for the reduced Simon equation and for a new, empirical melting equation.
Nuclear Superheat Quarterly Project Report: Sixth Quarter, October-December 1960
From introduction: "This is the sixth of 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."
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.
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."
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.
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."
High Power Density Development Project: Interim Report, 300 MWe HPD Conceptual Design Study
From introduction: "Preliminary design and analysis of the 300 MWe core."
Nuclear Superheat Quarterly Project Report: Eleventh Quarter, January-March 1962
From introduction: "This is the eleventh of 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."
Nuclear Superheat Quarterly Project Report: Fourth Quarter, April-June 1960
From introduction: "This is the fourth of 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."
Evaluation of Failed Hot Gas Isostatic Pressed Fuel Rods
From introduction: "Evaluations to determine cause of fuel rods breakage following irradiation."
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.
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."
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."
Extension of Programs for Calculations of Great Circle Paths and Sunrise-Sunset Times
Modification of an earlier program to remove restrictions in calculating the short or long great circle path.
Secondary Shutdown Systems of Nuclear Power Plants
From foreword: "Summarizes current practice in the subject of secondary shutdown systems and evaluates the capabilities of the secondary shutdown systems that were examined."
VBWR Stability Test Report
Analysis of the stability of boiling water reactors.
NS Savannah Upgrading Analog Computer Analysis
From abstract: "This work amplified previous design studies by considering accidents of greater severity, automatic limiting devices to preclude safety action, and more realistic parameters based on operating experience."
A New Near-Zone Electric Field-Strength Meter
Design and performance of a new near-zone electric field-strength meter.
An Investigation of a "Dynamic" Theory for Mass Transfer
A new theory is proposed to evaluate individual mass-transfer coefficients without actual experiment.
Stress Corrosion Cracking in Uranium-Molybdenum Alloys
Investigation conducted to determine the cause of cracking, during tension, on the surface of tensile specimens of uranium-molybdenum alloys.
Spark-Source Mass Spectrometric Analysis of Common and Radiogenic Lead
Analysis that is fast and has extremely low levels of detection for more than forty elements that may be present in lead.
A Computer Program for Determining First-Collision Neutron Doses
Data processing program written to compute the neutron dose received by individuals exposed in a nuclear excursion.
The Design and Performance of Levitation Melting Coils
The purpose of this study was to provide a means for evaluating the various parameters involved in the design and performance of levitation coils.
Transistorized Pulse Counting Equipment
This instrument was designed primarily to meet the need for radiation monitoring equipment in chemical process areas where corrosive vapors exist.
A Versatile Spectrometer Magnet Power Supply
Early results from actual laboratory operation of a more versatile magnet supply.
Salt Bath Heat Transfer Rates for Uranium Plate
Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant
Cycle study performed on a closed loop Brayton cycle incorporating a gas-cooled nuclear reactor, regeneration, and compressor intercooling. The purpose of the study was to determine the effect of various cycle parameters on efficiency and cost.
The Cold Pressing of Sinterable UO₂
The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.
Evaluation of Diethers as Uranium Extractants
Report on the determination of several physical properties, pertinent to uranium extraction, for a number of ethers and related compounds.
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."
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."
Failure Test of a Double Chambered NaK-Filled Irradiation Capsule
Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.
Numerical Results for EGCR Moderator-Element Stress Problems
From introduction: "A recent report describes the development of a general program for the IBM Type 7090 electronic computer for calculating plane thermal stresses."
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."
Nuclear Superheat Quarterly Project Report: Twelfth Quarter, April-June 1962
From introduction: "This is the twelfth of 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."
Nuclear Superheat Project Fabrication, Irradiation and Evaluation of Superheat Fuel Element SH-1 and SH-2
The fabrication, irradiation and evaluation of the first two superheat fuel assemblies is described in detail. Experimental data indicate that, in general, the nuclear superheat fuel elements have performed satisfactorily under the testing conditions used. Certain problem areas which will influence future fuel element designs have been defined.