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Hazard Summary Report Experimental Breeder Reactor II (EBR-II)
From Forward: "This report describes the present conceptions of the Experimental Breeder Reactor-II as well as the safety procedures and precautions which are currently anticipated for its operation."
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.
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.
Preliminary Design Requirements Argonne Boiling Reactor (ARBOR) Facility
From Introduction: "Descriptions of the functional requirements of the facility, together with preliminary concepts of methods for meeting them, are presented in this prospectus."
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
Hazard report on the Experimental Boiling Water Reactor that covers the basic modifications to the plant as designed to increase the present operating design rating of 20 Mw(t) to a new rating of 100 Mw(t). Changes and additions to the plant, core, reactor vessel, and other major components are shown. An analysis of the effects of the changes on the performance and safety of the reactor is presented.
Hazards Evaluation Report Associated with the Operation of EBWR at 100 MW
From Introduction: "This hazards report covers the basic modifications to the EBWR plant as designed to increase the present operating design rating of 20 Mwt to a new rating of 100 Mwt. it is written as a supplement to ANL-5781 (the original hazards report) and follows the outline of that report for purposes of cross reference."
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
Terminal Report on the Mighty Mouse High-Flux Research Reactor Project
From Introduction: "More specifically, it describes the basic reactor complex, the problems involved, the various approaches pursued, the present status and estimated cost of the project, along with recommendations for future research and development essential to the successful culmination of the project."
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.
Hazards Summary Report on the Oxide Critical Experiments
Report describing a zero-power reactor facility (ZPR-VII), its systems, and associated hazards.
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.
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.
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)
Zero-Power Experiments on the Argonne Low Power Reactor (ALPR)
Report describing the zero-power experiments on the Argonne Low Power Reactor. It is a prototype of a natural-circulation, boiling-water-reactor nuclear power plant designed to supply the electrical power and space heat requirements of a proposed Auxiliary DEW Line radar station.
Initial Testing and Operation of the Argonne Low Power Reactor (ALPR)
From Introduction: "In this report data are presented on the various phases of the program, together with test results and recommendations for future plant improvements. The ALPR prototype has proven to be a stable and reliable nuclear power plant."
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.
Summary Report on the Hazards of the Argonaut Reactor
From Summary: "This report covers installation of Argonaut Reactor at the Du-Page site of the Argonne National Laboratory."
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.
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."
A Process for the Recovery of Uranium From Nuclear Fuel Elements Using Fluid-Bed Drying and Volatility Techniques
From Summary: "The work described in this report is the application of this process to the recovery of uranium from highly enriched, low uranium-zirconium alloy plate-type fuels."
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.
U.S. Participation in the OEEC Halden Reactor Project May 1959 to September 1960
From Introduction: "This report summarizes the activities of the OEEC Halden Reactor Project, Halden, Norway, during the period of participation in the project by the author, from May 21, 1959 to September 22, 1960. The review is presented here in the interest of completeness of this report, in an effort to provide an impression of the character of research being carried out at Halden."
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.
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."
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."
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.)
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.
Recrystallization in Rolled Uranium Sheet
From Introduction: "To overcome the difficulties another investigation has been carried out wherein the rolling stock was subjected to step reduction and annealing treatments designed to develop a small, uniform grain size prior to the final rolling at room temperature. The results of metallographic, dilatometric, and X-ray diffraction studies of this material are given."
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.
Status Report on the Argonne Advanced Research Reactor
From Introduction: "This is a status report on the interim design and development for an advanced research reactor (AARR) that will produce a maximum thermal neutron flux of 5 x 10 to the fifteenth power neutrons/ (cm2) (sec). As a result, this report also contains sections covering shielding, plant layout, fuel charging, maintenance, and auxiliary facilities."
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.
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.
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."
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.
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)
Experimental Breeder Reactor-II (EBR-II) Shield Design
Report describing the EBR-II shield and the methods employed in arriving at the final design. The major shield design problems for that reactor are enumerated and discussed.
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.
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.
Terminal Report on the Boiling Slurry Reactor Experiment (Slurrex)
From Introduction: "This report is a documentation, from inception in 1959 to termination in 1960, of the design and development effort by the Reactor Engineering Division pertinent to construction of an aqueous boiling slurry reactor design, the problems involved, and the various approaches pursued."
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).
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.
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.
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."
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).
Irradiation of an Aluminum Alloy-Clad Ceramic Pellet-Fueled Plate
From Introduction: "An experiment, designated MTR-W10, was designed to determine the effects of high burnup on the cladding and fuel of an aluminum-1% nickel alloy (M-388)-clad ceramic pellet-fuelded plate if the type manufactured at Argonne for the BORAX-IV core. Conditions of irradiation were selected to allow local boiling at the high flux end of the plate at a pressure of 600 psig."
A Report on Some Attempts to Case Centrifugally Fuel Elements of Small Diameter
From Abstract: "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."
Operational Tests of EBWR Vapor Recovery System
From Introduction: "This report describes tests conducted on EBWR to evaluate the vapor recovery system."
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."
A Shielded Metallograph for Remote Metallography
From Introduction: "This report presents the specific design requirements arising from these initial decisions, followed by description and keyed illustrations of the various features of the installation. The Bausch and Lomb Research Metallograph was the instrument chosen as being most readily adapted to the over-all plan."
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