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  Partner: UNT Libraries Government Documents Department
 Decade: 1960-1969
 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/
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/
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/
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 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 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/
Engineering development of fluid-bed fluoride volatility processes
No Description digital.library.unt.edu/ark:/67531/metadc40284/
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/
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/
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/
Gas-Cooled Reactors in the USA A Survey and Recommendation
Report that provides "an understanding of the status of gas-cooled reactors as used for unclassified applications" and determining "phases of advanced research and development needed in the field and from these to recommend a program for high-temperature, gas-cooled reactors" (p. 5). digital.library.unt.edu/ark:/67531/metadc11545/
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/
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/
Hazard Evaluation Report on the Fast Reactor Zero Power Experiment ZPR-III
Report documenting the fast zero power reactor experiment (ZPRG-III). This includes a description of the experiment and the reactor, hazards, and accidents. digital.library.unt.edu/ark:/67531/metadc11557/
Hazards Evaluation Report Associated with the Operation of EBWR at 100 MW
No Description digital.library.unt.edu/ark:/67531/metadc11529/
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/
Helium-Purification Unit for High-Purity Inert-Atmosphere Boxes
No Description digital.library.unt.edu/ark:/67531/metadc11570/
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/
Idaho Division Summary Report
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. digital.library.unt.edu/ark:/67531/metadc170898/
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. digital.library.unt.edu/ark:/67531/metadc170896/
Interim Report: Faret Experimental Program
No Description digital.library.unt.edu/ark:/67531/metadc11576/
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/
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. digital.library.unt.edu/ark:/67531/metadc67195/
Irradiation of an Aluminum Alloy-Clad Ceramic Pellet-Fueled Plate
No Description digital.library.unt.edu/ark:/67531/metadc11540/
A Liquid-Metal Heat-Transfer Experiment
No Description digital.library.unt.edu/ark:/67531/metadc11596/
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