UNT Libraries Government Documents Department - 1,399 Matching Results
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- 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.
- 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.
- 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.
- 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.
- Argonne National Laboratory Annual Report: 1957
- Report issued by the Argonne National Laboratory discussing the variety of work done at the laboratory during the year of 1957. This report includes tables, illustrations, and photographs.
- Argonne National Laboratory Annual Report: 1958
- Report issued by the Argonne National Laboratory discussing the variety of work done at the laboratory during the year of 1958. This report includes tables, illustrations, and photographs.
- Engineering, Construction and Cost of the Argonaut Reactor
- Report describing the Argonaut Reactor located at the Argonne National Laboratory. Photographs and descriptive drawings of the reactor are included.
- The Process Equipment and Protective Enclosures Designed for the Fuel Fabrication Facility: Facility #350
- Report issued by the Argonne National Laboratory discussing the design and construction of equipment for reactor fuels. As stated in the summary, "the report describes the development, prototype construction, methods of testing, and leak detection of a modular hood design to be used in housing equipment and processes for the Argonne National Laboratory Fuel Fabrication Facility" (p. 9). This report includes tables, illustrations, and photographs.
- The EBWR: Experimental Boiling Water Reactor
- Report issued by the Argonne National Laboratory discussing the Experimental Boiling Water Reactor (EBWR) power plant. Designs of the final EBWR power plant are presented. This report includes tables, illustrations, and photographs.
- Argonne National Laboratory Annual Report: 1956
- Report issued by the Argonne National Laboratory discussing the variety of work done at the laboratory during the year of 1956. This report includes tables, illustrations, and photographs.
- Two-Phase Air-Water Flow Phenomena
- Report issued by the Argonne National Laboratory discussing two-phase flow studies that were conducted "to obtain empirical density relationships and pressure drop friction factors for two-phase mixtures" (p. 11). This report includes tables, illustrations, and photographs.
- Lecture Notes on Reactor Shielding
- Report issued by the Argonne National Laboratory discussing the shielding of radiation produced by nuclear reactors. As stated in the introduction, "these lectures will be an attempt to discuss the design of a reactor shield and the solution of the associated shielding problems by simple hand-computing methods" (p. 19). This report includes tables, and illustrations.
- A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter
- Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.
- Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant
- Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.
- Irradiation of an Aluminum Alloy-Clad, Aluminum-Uranium Alloy-Fueled Plate
- Report issued by the Argonne National Laboratory discussing irradiation tests of an aluminum alloy-clad, aluminum-uranium alloy fuel plate. As stated in the introduction, "calculations were made to determine the lowest possible pressure which would allow the maximum possible local boiling on the plate and still assure a margin of safety against burnout" (p. 9). This report includes tables, illustrations, and photographs.
- 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.
- Summary of Meteorological Data Taken at Argonne National Laboratory, Du Page County, Illinois, July 1952 Through June 1953
- Report issued by the Argonne National Laboratory discussing meteorological data collected between 1952 and 1953. Wind, temperature, pressure, and precipitation studies are presented. This report includes tables, illustrations, and a map.
- Quarterly Progress Report on Reactor Development: 4000 program
- Report issued by the Argonne National Laboratory discussing progress made on reactor development. Progress made on the core, pressure vessel and shield, and the power plant are presented. This report includes tables, and illustrations.
- The Transient Behavior of Single-Phase Natural Circulation Water Loop Systems
- Report issued by the Argonne National Laboratory discussing single-phase water loop systems. As stated in the introduction, "the principal objective of this study was to determine the reliability of the calculations based upon numerical solutions of finite-difference energy and flow equations" (p. 9). This report includes tables, illustrations, and photographs.
- 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.
- 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.
- 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.
- Selected Values of the Physical Properties of Various Materials
- Report issued by the Argonne National Laboratory discussing selected physical properties of various solids, liquids, and gases of interest in nuclear reactor heat transfer and fluid flow analysis. In most cases, values for thermal conductivity specific heat, density, viscosity, and Prandtl numbers are given as functions of temperature. This report includes tables, and illustrations.
- Argonne High-Flux Research Reactor: AHFR Conceptual Design Study
- Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.
- Summary of Conference on the Toxicity of Carbon 14 Held at Argonne National Laboratory, January 15-16, 1952
- Report issued by the Argonne National Laboratory discussing the Conference on the Toxicity of Carbon 14. At the outset of the meeting it was emphasized that the group was brought together to discuss work which had a bearing on the toxicity of C14 compounds used either clinically or industrially, and the hope was expressed that the group might be able to reach some conclusions on these matters. This report includes tables.
- Heat Generation in Irradiated Uranium
- Report issued by the Argonne National Laboratory discussing the heat generation of irradiated uranium. Methods of heat production in uranium are presented. This report includes tables, and illustrations.
- Electronic Distribution Functions and Thermodynamic Properties at High Temperatures
- Report issued by the Argonne National Laboratory discussing the thermodynamics and electronic distribution of high temperatures. As stated in the introduction, "in the present paper, a model for computing is described which takes into account in detail the interactions between bound electrons and the average interaction of the bound electrons with the free ones" (p. 4). This report includes tables, and illustrations.
- Engineering Properties of Diphenyl
- Report issued by the Argonne National Laboratory discussing engineering properties of diphenyl. As stated in the abstract, "data collected from the literature on the vapor pressure, enthalpy, liquid density, and vapor density of pure diphenyl are presented. A Mollier diagram, a temperature entropy diagram, and data on viscosity of diphenyl as a function of temperature are also presented" (p. 5). This report includes tables, and illustrations.
- A Physical Determination of the Conversion Ratio of the Experimental Breeder Reactor
- Report issued by the Argonne National Laboratory discussing the Experimental Breeder Reactor (EBR). Descriptions and methods of the EBR are presented. This report includes tables, and illustrations.
- Progress Report on the Argonne-Oak Ridge Digital Computer
- Report issued by the Argonne National Laboratory discussing a progress report on the Argonne-Oak Ridge digital computer. This report is an interim report, whose primary value is that it has forced those engaged in the work to give concrete expression to what they have been doing and thinking about up to this point. This report includes tables, illustrations, and photographs.
- Reactor Development Program Progress Report: March 1963
- Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
- 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.
- 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.
- 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.
- 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.
- Argonne National Laboratory Metallurgy Division Annual Report: 1963
- Annual report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963 including progress related to experiments, programs, and studies. This report includes tables, illustrations, and photographs.
- Quarterly Report February, March, April, 1949: Biological and Medical Divisions
- Report issued by the Argonne National Laboratory discussing the progress and work completed between February and April, 1949. Descriptions of the studies conducted and progress made are presented. This report includes tables, illustrations, and photographs.
- Reactor Engineering Division Quarterly Report: December 1, 1953 Through March 30, 1954
- Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
- Particle Accelerator Division Summary Report: April Through September 1960
- Report issued by the Argonne National Laboratory discussing a summary report of the Particle Accelerator Division. As stated in the summary, "this report outlines two methods applicable respectively to longhand and computer calculations" (p. 4). This report includes tables, illustrations, and photographs.
- Argonne National Laboratory Idaho Division Summary Report: July-September, 1960
- Report issued by the Argonne National Laboratory covering a summary report of the work conducted by the Idaho Division. Experimental work and progress made on reactors are presented. This report includes tables, illustrations, and photographs.
- Argonne National Laboratory Idaho Division Summary Report: October 1960-March 1961
- Report issued by the Argonne National Laboratory discussing a summary of projects conducted with the Idaho Division. Descriptions of each project are presented. This report includes tables, and illustrations.
- Particle Accelerator Division Summary Report: April 15, 1958 through October, 1958
- Report issued by the Argonne National Laboratory discussing a summary report of work completed between April and October, 1958. Summaries of the studies conducted and work completed are presented. This report includes tables, and illustrations.
- 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.
- A Study of Convective Magnetohydrodynamic Channel Flow
- Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.
- Self-Sustained Hydrodynamic Oscillations in a Natural Circulation Two-Phase-Flow Boiling Loop
- Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.
- Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow
- Two-phase flow-regime transitions at elevated pressures for a single-component, trichloromonofluoromethane, were investigated for forced-circulation, upward flow in a vertical, rectangular conduit with internal dimensions of 0.380 by 1.050 inches.
- A Multiple-Source Urban Atmospheric Dispersion Model
- Report documenting the development phase of a multiple-source, urban atmospheric dispersion model that describes environmental transients.
- Reactor Engineering Division Quarterly Report, June 1, 1949 - August 31, 1949
- Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
- The Relative Thermal Conductivities of Liquid Lithium, Sodium, and Eutectic NaK, and the Specific Heat of Liquid Lithium
- Report discussing the relative thermal conductivities of liquid lithium, sodium, and eutectic NaK, and the specific heat of liquid lithium, as well as the methods and materials used to determine this information.
- FORTIO: a FORTRAN I/O Interface
- A set of OS/370 Basic Assembly Language programs is described which provides a FORTRAN IV interface with OS/370 Macros.