UNT Libraries Government Documents Department - 67 Matching Results

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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.
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 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.
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.
Idaho Division Summary Report: July, August, 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 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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
Heat Transfer, Flow Instability, and Critical Heat Flux For Water in a Small Tube At 200 psia
From Abstract: Report discussing "the effects of developing two-phase flow regimes in a constant-pressure drop system are shown in recorded traces from a fast-response flow transducer: the mass velocity decreases and transfer-surface superheat increases with increasing steam quality."
An Ultrasonic Measurement System for The Precise Determination of the Elastic Moduli of Single Crystals
From Abstract: "The equipment described in this paper is based on the technique developed by McSkimin. Figure 1 shows a block diagram of the system. The oscilloscope presentation with no specimen present appears as shown in Figure 2a. At discrete frequencies, the pattern appears as shown in Figure 2b."
Interim Report: Faret Experimental Program
From Introduction: "The Fast Reactor Test (FARET) program is part of the United States Fast Reactor Program directed toward the demonstration of breeder reactors essential to the long-range goal of utilizing fertile fuels. (1) With-in this program is the current thinking that the early construction and operation of two or three prototype nuclear power plants of the order of 250 Mw(e) will lead eventually to the construction of practical and economic full scale breeder reactors by the early 1980's. (2)"
Transient Behavior of a Natural-Circulation Loop Operating Near The Thermodynamic Critical Point
From Introduction: "Interest in utilizing natural-circulation loops to obtain results that aid in the design of some boiler and nuclear reactor coolant systems has focused attention on the dynamic behavior of such loops. Much analytical and experimental work has been done so as to permit predictions of the transient behavior of both single-phase and two-phase neutral-circulation systems. The analytical portion of the study consisted of simulating the loop by utilizing a digital computer to predict the measured transients."
Proceedings of the AMU-ANL Summer Study Program
From Introduction: "In 1954, the AEC presented the "five-year plan" for power reactor development, briefly outlined in Table I-1. The program proceeded and other reactors were added as a result of the incentives indicated in the outline."
Optimization of Efficiency of a Cesium Diode Converter
From Introduction: "The efficiency of the converter is computed with the least possible assumptions. Thermal emissivity and the interelectrode heat-transfer coefficient are varied, and the effect on efficiency is investigated."
Two-Phase Heat Transfer With Gas Injection Through A Porous Boundary Surface
From Introduction: "The purpose of this study is to investigate some of the hydrodyamic aspects of two-phase heat transfer in the lower quality range. The results of this study should contribute to a better and more thorough understanding of the processes and mechanisms affecting two-phase heat transfer, and in this way help in improving its prediction."
Pictorial Studies of Molecules 1: Molecular Orbital Density Comparisons of H2, Li2, B2, C2, N2, O2, and F2
From Review of Theory: " In practice, a very close approximation to the molecular orbitals can be obtained in this way. Recent calculations of this type, utilizing analysis and computer programs developed by the author, have resulted in the determination of the molecular orbitals for a large number of diatomic molecules in the form of Eq. (2). These functions, which are thought to be very close to the Hartree-Fock (i.e., the molecular orbitals demanded by theory) result, were used in the pictorial calculations presented in this report."
XLIBIT: ANL Cross-section Library Code
From Introduction: "With the acquisition by the Laboratory of a Control Data 3600 computer in the fall of 1963, a joint reprogramming project was undertaken by the Laboratory's Applied Mathematics Division and the Control Data Corporation to develop one - and two-dimensional diffusion-theory and Sn transport-theory programs for the CDC-3600. The XLIBIT code described in this report was developed as a part of this project. XLIBIT is a CDC-3600 program designed to: 1) Prepare a cross-section library tape. 2) Modify an existing cross-section library tape. 3) Duplicate an existing cross-section library tape. 4) Print all or a portion of the cross-section data on the library tape. Punch cross-section decks for all or a portion of the data on the library tape. The decks produced are identical to those used in pertaining the tape."