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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: Argonne National Laboratory Reports
LMFBR Nuclear Safety Program Annual Report: July 1, 1969, to June 30, 1970
Report issued by the Argonne National Laboratory discussing the Liquid Metal Fast Breeder Reactor Nuclear Safety Program. The work completed by the program between 1969 and 1970 is presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc67207/
Pressure-Pulse Propagation in Two-Phase One- and Two-Component Mixtures
Report issued by the Argonne National Laboratory discussing the propagation velocity of pressure pulses in two-phase mixtures. As stated in the abstract, "in this study, a comprehensive analytical development of the propagation velocity of small pressure pulses is presented for bubble, annular, stratified, droplet, and slug-flow regimes. Particular attention is given to the influence of flow regime on the momentum transfer between phases" (p. 9). This report includes tables, illustrations, and a photograph. digital.library.unt.edu/ark:/67531/metadc67206/
Survey and Status Report on Application of Acoustic-Boiling-Detection Techniques to Liquid-Metal-Cooled Reactors
Report issued by the Argonne National Laboratory discussing acoustic-boiling-detection techniques. As stated in the abstract, "this report summarizes literature through June 1967 concerning acoustic methods. In the acoustic method for boiling detection, either acoustic waveguides or high-temperature acoustic sensors are recommended" (p. 1). This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc67204/
Midwest Tandem Cyclotron: A Proposal for a Regional Accelerator Facility
Report issued by the Argonne National Laboratory discussing the proposal of the Midwest Tandem-Cyclotron accelerator facility. Descriptions of the facility designs, methods, and operations are presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc67205/
Design and Testing of a High-Heat Flux Electron-Bombardment Heater
Report issued by the Argonne National Laboratory discussing the testing of an electron-bombardment heater. As stated in the abstract, "the applications of electron-bombardment heating to liquid-metal heat transfer and reactor safety experiments are discussed. The design of a high-heat-flux, electron-bombardment heater (EBH) is presented" (p. 7). This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc67203/
A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments
Report issued by the Argonne National Laboratory discussing a computer program used for fast reactor safety experiments. As stated in the summary, "this report gives a detailed description of a hybrid-computer program for calculating temperatures in a multi-region, axisymmetric, cylindrical configuration consisting of solid materials bounded by flowing coolant. Included is an explanation of the mathematical methods, together with a discussion of special features, input-output descriptions, and several sample problems" (p. 7). This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc67202/
The Expulsion of Liquid from a Rapidly Heated Channel
Report documenting experiments in order to determine the "behavior of a partially confined liquid in contact with a rapidly heated surface" (p. 7). These liquids include water, methanol, ethylene bromide, and acetone. digital.library.unt.edu/ark:/67531/metadc101031/
On The Steady-State Thermal Stresses in Cylindrical Fuel Pins Due to Axial Variations in Their Internal Heat-Generation Rate
No Description digital.library.unt.edu/ark:/67531/metadc11604/
Reactor Development Program Progress Report: September 1966
Report issued by the Argonne National Laboratory discussing progress made within the Reactor Development Program for September, 1966. The report includes highlights of the different project activities including plutonium utilization, fast breeder reactors, general reactor technology, advanced systems research, and nuclear safety. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc170910/
Reactor Development Program Progress Report: May 1966
Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during May 1966. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc170908/
The Electrical Design of the EBR-II
Report that "summarizes the electrical design of the Experimental Breeder Reactor II Facility (EBR-II). It attempts to gather together and present in reasonable detail the essential features and workings of the completed design, and to present a concise overall view of the system" (p. 11). digital.library.unt.edu/ark:/67531/metadc11603/
A Computer Program for the Kinetic Treatment of Radiation-Induced Simultaneous Chemical Reactions
No Description digital.library.unt.edu/ark:/67531/metadc11602/
A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction
Report issued by the Argonne National Laboratory discussing the PACER-65 computer program. As stated in the summary, the program "has been developed and utilized for flow sheet calculations and process-data reduction. PACER-65 is an executive program in which material- and energy-balance equations, conversion factors, etc., for each processing step are described by separate subroutines" (p. 5). This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc67201/
XLIBIT: ANL Cross-section Library Code
No Description digital.library.unt.edu/ark:/67531/metadc11601/
Reactor Development Program Progress Report: November 1965
Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during November 1965. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc170906/
The Mass Transfer of Single, Solid Uranium Spheres to Flowing Molten Cadmium in Laminar and Turbulent Flow
No Description digital.library.unt.edu/ark:/67531/metadc11600/
Pictorial Studies of Molecules 1: Molecular Orbital Density Comparisons of H2, Li2, B2, C2, N2, O2, and F2
No Description digital.library.unt.edu/ark:/67531/metadc11599/
A Liquid-Metal Heat-Transfer Experiment
No Description digital.library.unt.edu/ark:/67531/metadc11596/
Liquid MHD Power Cycle Studies
Report issued by the Argonne National Laboratory discussing the magnetohydrodynamics (MHD) power cycle for liquid metals. The benefits, and different phases of the MHD power cycle are presented. This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc67200/
Propagation of Density Disturbances in Air-Water Flow
No Description digital.library.unt.edu/ark:/67531/metadc11598/
Frequency-Response Analysis of Steam Voids to Sinusoidal Power Modulation in a Thin-Walled Boiling Water Coolant Channel
Report regarding a study with the primary objective of acquiring "experimental data on power-to-void transfer functions for a single rectangular flow channel at elevated pressures" (p. 9). digital.library.unt.edu/ark:/67531/metadc11597/
An Investigation of Instabilities Encountered During Heat Transfer to a Supercritical Fluid
Report concerning "the unstable behavior of a heat-transfer loop operating at a super-critical pressure (p. 7)" within a nuclear reactor. digital.library.unt.edu/ark:/67531/metadc11595/
Analytical and Experimental Investigation of a Nuclear Reactor Support Structure
Report containing experiments regarding the slopes and deflections of different grid support structures for a nuclear reactor. digital.library.unt.edu/ark:/67531/metadc11584/
Spectral representation and criticality problem of a two-region cell transport operator
No Description digital.library.unt.edu/ark:/67531/metadc40283/
Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation
Report issued by the Argonne National Laboratory discussing condensation theories of metal vapors. As stated in the introduction, "the objectives of this research then are critical analysis of condensation theories and data for metal vapors and experimental evaluation of the resistance to condensation for a representative metal such as mercury" (p. 18). This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc67199/
The Graetz Problem in Cocurrent-Flow, Double-Pipe, Heat Exchangers
Report showing "that the Graetz Problem pertaining to the cocurrent-flow, double-pipe, heat exchanger can be studied analytically by extensions of familiar mathematical techniques" (p. 7). digital.library.unt.edu/ark:/67531/metadc11593/
Preliminary Physics and Heat Transfer Design Calculations for a Rocket Fuel Test Reactor (RFTR)
No Description digital.library.unt.edu/ark:/67531/metadc11586/
The Control of Condensation Heat Transfer Rates Using an Electromagnetic Field
Report issued by the Argonne National Laboratory over "the use of an electromagnetic field to control the laminar film condensation of a vapor whose liquid is electrically conducting" (p. 7). This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc11589/
Performance Characteristics of a Liquid Metal MHD Generator
Report issued by the Argonne National Laboratory discussing the performance of magnetohydrodynamic generators. As stated in the abstract, "an experimental study was made of the performance characteristics of a liquid metal MHD generator utilizing single-phase sodium-potassium and two-phase sodium-potassium-nitrogen fluids. The purpose of this study was to compare the generator performance with theory for single-phase flow and to determine the effects of the introduction of the gaseous phase on the generator output and efficiency" (p. 9). This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc67196/
Bending of Circular Plates Under A Uniform Load on a Concentric Circle
Report containing "analyses of thin, flat, circular plates subject to bending" (p. 7) using various equations for use as equipment for the Argonne National Laboratory Zero Gradient Synchrotron. digital.library.unt.edu/ark:/67531/metadc11594/
Bending of Circular Plates Under A Variable Symmetrical Load
Report containing "analyses of thin, flat, circular plates subject to bending" (p. 7) using various equations for use as equipment for the Argonne National Laboratory Zero Gradient Synchrotron. digital.library.unt.edu/ark:/67531/metadc11592/
Dynamic Analysis of Coolant Circulation in Boiling Water Nuclear Reactors
Report concerning the study of the two-phase flow through the cooling channels of a natural-circulation boiling water nuclear reactor. "One-dimensional conservation equations describing the flow through each channel are written in the linearized perturbed form, and Laplace transformation in time is performed." (p. 5) digital.library.unt.edu/ark:/67531/metadc11587/
The Period Effect in Reactor Dynamics
No Description digital.library.unt.edu/ark:/67531/metadc11588/
Application of Electron-Bombardment Heating for Boiling Liquid Metals
Report discussing the "problem of obtaining a curve of the heat flux vs. temperature difference for boiling liquid metals" (p. 3). Contains discussions of a variety of heating techniques, though it focuses on electron-bombardment heating. digital.library.unt.edu/ark:/67531/metadc11591/
Two-Phase Heat Transfer With Gas Injection Through A Porous Boundary Surface
No Description digital.library.unt.edu/ark:/67531/metadc11590/
Annual Report for 1963: Metallurgy Division
Report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963. Annual experiments, programs, and studies are presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc170918/
Development of Techniques for Fabrication of Small-Diameter Thin-Wall Tungsten Tubing: Interim Progress Report covering the period from July 1, 1963 through December 31, 1963
Report describing the methods and equipment used to extrude tungsten tubing from various starting materials. digital.library.unt.edu/ark:/67531/metadc11585/
Engineering development of fluid-bed fluoride volatility processes
No Description digital.library.unt.edu/ark:/67531/metadc40284/
Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat
Report describing the development, fabrication, and nondestructive and destructive evaluation of stainless steel-clad fuel plates, the evaluation of fuel subassemblies, and the assembly of fuel element components at Argonne National Laboratory. digital.library.unt.edu/ark:/67531/metadc11569/
Safety Analysis Report, Argonne Fast Critical Facility (ZPR-VI)
Report by the Argonne National Laboratory evaluating the Argonne Fast Critical Facility, ZPR-VI, under construction during the course of the study. The study addresses various functionalities and safety features of the facility. digital.library.unt.edu/ark:/67531/metadc11547/
A Method of Calculating Transient Temperatures in a Multiregion, Axisymmetric, Cylindrical Configuration the Argus Program, 1089/Re248, Written in Fortran II
No Description digital.library.unt.edu/ark:/67531/metadc11571/
A Performance Analysis of the EBWR at Various Power Levels
No Description digital.library.unt.edu/ark:/67531/metadc11579/
Two-Phase Critical Flow With Application to Liquid-Metal Systems (Mercury, Cesium, Rubidium, Potassium, Sodium, and Lithium)
No Description digital.library.unt.edu/ark:/67531/metadc11582/
Breeding-Gain Specimens for EBR-I Core IV
Report issued by the Argonne National Laboratory over studies conducted on uranium and plutonium specimens used in fuel rods. The results are presented and discussed. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc11572/
A Survey of Prompt-Neutron Lifetimes in Fast Critical Systems
No Description digital.library.unt.edu/ark:/67531/metadc11574/
An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle
Report that "describes an investigation of the flow characteristics in a horizontal, converging-diverging nozzle for a two-phase, two-component system" (p. 1) using air and water and "attempting to determine the effects of accelerating the liquid phase by the gaseous phase" (p. 1). digital.library.unt.edu/ark:/67531/metadc11583/
Development of an Electrical Resistivity Probe For Void-Fraction Measurements in Air-Water Flow
No Description digital.library.unt.edu/ark:/67531/metadc11580/
Heat Transfer, Flow Instability, and Critical Heat Flux For Water in a Small Tube At 200 psia
No Description digital.library.unt.edu/ark:/67531/metadc11578/
A Practical Approach to Availability and Irreversibility
No Description digital.library.unt.edu/ark:/67531/metadc11581/
Reactor Development Program Progress Report: April 1963
Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc170903/
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