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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: Argonne National Laboratory Reports
Addendum to Hazard Summary Report Experimental Breeder Reactor-II (EBR-II)
Report containing hazard and safety information regarding the Experimental Breeder Reactor-II in Idaho. digital.library.unt.edu/ark:/67531/metadc11522/
Advanced Designs of Magnetic Jack-Type Control Rod Drive
Report containing information regarding magnetic jacks, which are devices used "for positioning the control rods in a nuclear reactor, especially in a reactor containing water under pressure" (page 9). Contains a description of the device, its use, test results, and illustrations. digital.library.unt.edu/ark:/67531/metadc11533/
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/
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/
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/
Argonaut Automatic Flux Controller Design Report
Report issued by the Argonne National Laboratory over design studies conducted on Argonaut reactors for training and research purposes. As stated in the abstract, "the design presented in the form of a steady-state analysis based upon the small-signal linearization of the reactor kinetics transfer function. The measured controller performance and construction details of the equipment is given" (p. 7). This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc11537/
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. digital.library.unt.edu/ark:/67531/metadc67190/
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. digital.library.unt.edu/ark:/67531/metadc67182/
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. digital.library.unt.edu/ark:/67531/metadc67183/
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. digital.library.unt.edu/ark:/67531/metadc67184/
Automatic Foil Activity Counting Facility and Data-Reduction Program
No Description digital.library.unt.edu/ark:/67531/metadc11567/
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/
Boiling Water Reactor Technology Status of the Art Report: Volume 1., Heat Transfer and Hydraulics
Report discussing state of the art design and operation of heat transfer and hydraulics equipment and technology in boiling water reactor power plants. digital.library.unt.edu/ark:/67531/metadc11563/
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/
Calculations on U235 Fission Product Decay Chains
Report of equations for calculating decay of U235. The introduction states" Calculations have been made on the U235 fission product decay schemes. The results for a typical example, that of a reactor operating at 1000 kilowatts for 180 days, have been tabulated and graphed. General formulae have been used so that the results can be applied for any power level and any time of irradiation" (p. 2). digital.library.unt.edu/ark:/67531/metadc40281/
Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements
Report issued by the Argonne National Laboratory over studies conducted on the Argonne Low Power Reactor. As stated in the abstract, "this report describes the manufacture of 1150 fuel core blanks, of which 816 were used in the fabrication of fuel elements. Development, casting, hot and cold rolling, cleaning, and punching of core blanks are discussed, as are nondestructive testing and evaluation of the manufacturing processes" (p. 7). This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc11532/
A Computer Program for the Kinetic Treatment of Radiation-Induced Simultaneous Chemical Reactions
No Description digital.library.unt.edu/ark:/67531/metadc11602/
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 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/
Corrosion Studies of Ternary Zirconium Alloys in High-Temperature Water and Steam
Report concerning the corrosion of several ternary zirconium alloys using distilled water at 350 degrees Celsius or ssteam heated to 540 degrees Celsius and 600 psi. digital.library.unt.edu/ark:/67531/metadc11555/
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. digital.library.unt.edu/ark:/67531/metadc67194/
Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)
Report regarding "[t]he Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyro-metallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5 percent fissium and contains about 46 wt.% Uranium-235 . The blanket material consists of uranium in which plutonium is bred. Core and blanket subassemblies contained in transfer coffins are transferred between EBR-II and the Fuel Cycle Facility, which is in an adjacent building." (p. 13) digital.library.unt.edu/ark:/67531/metadc11564/
Design and Hazards Summary Report Boiling Reactor Experiment V (BORAX V)
Report describing the design and usage of the BORAX V nuclear reactor, its surrounding facility, systems, experimental programs, and possible hazards. digital.library.unt.edu/ark:/67531/metadc11551/
Design and Performance Characteristics of Magnetic Jack-Type Control Rod Drive
Report concerning the design of the magnetic jack, which is a "hermetically sealed, step-motion linear motor which satisfies the need for a reliable, low-cost, nuclear reactor control rod drive." (p. 5) digital.library.unt.edu/ark:/67531/metadc11527/
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/
Design of the Argonne Low Power Reactor (ALPR)
Report containing "[a] description (...) of the design of a prototype "packaged" nuclear power plant. The purpose of the plant is to alleviate fuel oil logistics and storage problems posed by remote auxiliary DEW Line radar stations north of the Arctic Circle. The ALPR (redesignated SL-1) is a 3 Mwt, heterogeneous, highly enriched uranium- fueled, natural-circulation boiling water reactor, cooled and moderated with light water. Steam at 300 psig, dry and saturated (421 deg F) is passed directly from the reactor to a conventional turbine-generator to produce electric power (300 kw nominal) and space-heating (400 kw) requirements consistent with rigid mechanical and structural specifications prescribed by the military, and dictated by the extreme geophysics prevailing at the ultimate site. The over-all design criteria emphasize: simplicity and reliability of operation and maintenance, with minimum supervision; minimum on-site construction; maximum use of standard components; limited water supply; utilization of local gravel for biological shielding; transportability by air lift; and nominal 3-year fuel operating lifetime per core loading." (p. 15) digital.library.unt.edu/ark:/67531/metadc11534/
Design Summary Report on the Juggernaut Reactor
Report issued by the Argonne National Laboratory over design studies conducted on the Juggernaut reactor. Design processes, and methods are presented and discussed. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc11566/
Development of an Electrical Resistivity Probe For Void-Fraction Measurements in Air-Water Flow
No Description digital.library.unt.edu/ark:/67531/metadc11580/
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/
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/
EBR-II Dry Critical Experiments Experimental Program, Experimental Procedures, and Safety Considerations
Report containing zero power (<1 kw) Dry Critical Experiments that were "to be conducted in the EBR-II Reactor prior to filling the Primary System with sodium coolant" (p. 7.) The two primary objectives of these experiments were to determine how well the system performed without sodium coolant and to "determine and/or verify certain operational data to permit modification or improvement of the system (neutron shield, instrumentation, etc.) prior to the introduction of sodium into the system" (p. 7.) digital.library.unt.edu/ark:/67531/metadc11550/
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. digital.library.unt.edu/ark:/67531/metadc67181/
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/
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. digital.library.unt.edu/ark:/67531/metadc67174/
Engineering, Construction and Cost of the Argonaut Reactor
No Description digital.library.unt.edu/ark:/67531/metadc67185/
Engineering development of fluid-bed fluoride volatility processes
No Description digital.library.unt.edu/ark:/67531/metadc40284/
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. digital.library.unt.edu/ark:/67531/metadc67175/
An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters
Report estimating the merits of a variety of nuclear reactor concepts for use as external superheaters to be added on to a steam-producing nuclear power plant. digital.library.unt.edu/ark:/67531/metadc11558/
Experimental Breeder Reactor-II (EBR-II) Shield Design
No Description digital.library.unt.edu/ark:/67531/metadc11565/
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/
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/
The Fabrication of Certain Jacketed Uranium Helices
Report describing the fabrication of Doppler Helices, which were 1/8 inch diameter x 12 foot long uranium core completely enclosed within a thin metal jacket and wound into a spring or helix shape. digital.library.unt.edu/ark:/67531/metadc11518/
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/
The Facility 350 Helium-Atmosphere System
Report describing the helium atmosphere system in the Argonne National Laboratory's Facility 350. The atmosphere's ability to remove moisture, oxygen, and other impurities, how the atmosphere is purified, and experimental data regarding the use of activated carbon to absorb oxygen from helium are discussed. digital.library.unt.edu/ark:/67531/metadc11561/
Facility For Photographing in-Pile Meltdown Experiments in TREAT
Report regarding the fabrication of a transparent meltdown facility for the purpose of photographing simulated meltdowns. digital.library.unt.edu/ark:/67531/metadc11560/
Fast Fuel Test Reactor - FFTR Conceptual Design Study
Report describing the design of a Fast Fuel Test Reactor (FFTR), analyses of of the reactor's operations, related costs, and possible future projects. digital.library.unt.edu/ark:/67531/metadc11543/
Five-year climatological summary, July 1949-June 1954, Argonne National Laboratory, DuPage County, Illinois
Report documenting various meteorological measurements for the purpose of understanding the possible dispersion of radioactive material. digital.library.unt.edu/ark:/67531/metadc11513/
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/
Frequency Response Measurements of the EBWR Automatic Steam by-Pass Valve Control System
Report describing the steam by-pass system of the Economic Simplified Boiling Water (EBWR) Reactor. The control system and errors are described. digital.library.unt.edu/ark:/67531/metadc11524/
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