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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.
Hazard Summary Report on the Experimental Boiling Water Reactor (EBWR)
Report discussing possible hazards and preliminary safeguards for a 20-megawatt Experimental Boiling Water Reactor (EBWR) power plant
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)
Experimental Breeder Reactor-II (EBR-II) Shield Design
No Description Available.
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)
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.
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).
Development of an Electrical Resistivity Probe For Void-Fraction Measurements in Air-Water Flow
No Description Available.
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.
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)
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.
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.
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.
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.
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.
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.)
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.
Hazards Summary Report on the Oxide Critical Experiments
Report describing a zero-power reactor facility (ZPR-VII), its systems, and associated hazards.
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.
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.
A General Method for Comparing Thermal Performance of Fuel Element Geometries and Coolants for Non-Boiling Reactors
Report containing a method "for comparing the influence of various fuel element geometries on rector core shape or different specifications of thermal performance"(p. 7).
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).
A Computer Program for the Kinetic Treatment of Radiation-Induced Simultaneous Chemical Reactions
No Description Available.
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.
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).
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.
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.
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.
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)
Hazards Evaluation Report Associated With the Operation of EBWR at 100 MW
No Description Available.
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.
A Lunar Power Plant
Report issued by the Argonne National Laboratory over studies conducted on designs for a lunar power plant. As stated in the abstract, "a concept of a nuclear power plant to be assembled on earth and operated on the moon in presented" (p. 9). This report includes tables, illustrations, and photographs.
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.
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).
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.
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.
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.
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.
Transistor Scintillation Spectrometer
Report describing "an AC-operated portable scintillation spectrometer consisting of a preamplifier, a linear pulse amplifier, a single-channel pulse-height analyzer, a linear count-rate meter, a scaler, and a high-voltage power supply. The operation and performance of the circuits are discussed" (p. 3).
Zero-Power Experiments on the Argonne Low Power Reactor (ALPR)
No Description Available.
Automatic Foil Activity Counting Facility and Data-Reduction Program
No Description Available.
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.
Hazard Summary Report on the Argonne Low Power Reactor (ALPR)
Report regarding a nuclear reactor designed to operate in arctic conditions. This report includes a design of such a reactor and potential hazards.
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).
A Low Dead-Time Neutron-Counting-System
From Abstract: "This report describes a counting system capable of processing input pulses at an average rate in excess of 3 x 10 to the fifth power counts per second with less than 10 percent counting loss due to instrumental dead time."
A Performance Analysis of the EBWR at Various Power Levels
From Introduction: "This study is an attempt to predict the operating performance of EBWR (Experimental Boiling Water Reactor) at various power levels. It was done at the same time that EWBR was raised in power up to 100 MW, and so an excellent possibility was given to check the validity of the used performance analysis. Rather than giving a general and complete outline of the analysis or establishing a new approach, the study outlines and specifies the numerous practical problems involved in this analysis, and tries to explain the discrepancies between predicted and experimental results."
Manufacture of Fuel Plates for the Experimental Boiling Water Reactor
From Abstract: "Discussed in the paper are the production of the uranium fuel alloy, the fabrication of the cladding components from Zircaloy-2 ingot, the assembly, welding, evacuation, and sealing of the cladding billets, the jacketing of the cladding billets with steel, and the roll bonding, heat treatment, stripping, and cleaning of the fuel plates. Evaluation of the fuel plates produced is also included."
Thermal Hydraulic Performance Characteristics of EBWR (0 to 100 Mwt)
From Introduction: "As a result, the modification of the EBWR internals for operation at higher power was directed primarily toward achieving this goal. The major modifications that were made are described briefly below."
Preliminary Design of a Basic Radiation Effects Reactor (BRER)
From Introduction: "Information has been accumulated about the property changes produced, but there are essentially no reliable quantitative data correlating property changes with the magnitude and energy distribution of the neutron fluxes responsible for the changes. The design of the Basic Radiation Effects Reactor (BRER) presented herein stems from the two main requirements: 1. a fairly high-level, high-energy neutron flux with minimal thermal neutron and gamma-ray background is desired; 2. the peak of the neutron-energy spectrum should be variable within the approximate range from 10 to 1000 kev."
Preliminary Design and Hazards Report-Boiling Reactor Experiment V (BORAX V)
From introduction: "The report is preliminary. At the time of writing, the status of the BORAX V project is that design of the reactor buildings and plant, done in collaboration with the architect-engineer with the architect-engineer has been completed and construction has just started; however, the mechanical design of the fuel and cores is still tentative."