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  Partner: UNT Libraries Government Documents Department
 Collection: Technical Report Archive and Image Library
On the Calibration of Cascade Impactors
No Description
Aeroradioactivity Survey and Areal Geology of the Georgia Nuclear Laboratory Area, Northern Georgia (ARMS-I)
Report regarding an airborne gamma-radioactivity survey that took place over a 7,000 square mile area around the George Nuclear Laboratory in Dawson County, Georgia. Topics include the types of bedrock noted in the area as well as their levels of radioactivity.
Standard X-ray Diffraction Powder Patterns: Section 18. Data for 58 Substances
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Aeroradioactivity Survey and Areal Geology of the Hanford Plant Area, Washington and Oregon (ARMS-I)
Report regarding an airborne gamma-radioactivity survey that took place over a 9,000 square mile area in south-central Washington and north-central Oregon. Topics include the types of bedrock noted in the area as well as their levels of radioactivity.
Summary of Available Data on the Strontium 90 Content of Foods and of Total Diets in the United States
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Ultramicro Methods in Biochemistry: [Part] 1. General Consideration, [Part] 2. Procedures for the Determination of Serum Bilirubin
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MeV Total Neutron Cross Sections
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Thermal Conductivity of Solids At Room Temperature and Below: A Review and Compilation of the Literature
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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.
Terminal Report on the Mighty Mouse High-Flux Research Reactor Project
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Initial Testing and Operation of the Argonne Low Power Reactor (ALPR)
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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
Preliminary Design and Hazards Report-Boiling Reactor Experiment V (BORAX V)
No Description
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
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.
Preliminary Physics and Heat Transfer Design Calculations for a Rocket Fuel Test Reactor (RFTR)
No Description
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).
Two-Phase Critical Flow With Application to Liquid-Metal Systems (Mercury, Cesium, Rubidium, Potassium, Sodium, and Lithium)
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A Practical Approach to Availability and Irreversibility
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Development of an Electrical Resistivity Probe For Void-Fraction Measurements in Air-Water Flow
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The Period Effect in Reactor Dynamics
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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
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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.
Proceedings of the AMU-ANL Summer Study Program
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Status Report on the Argonne Advanced Research Reactor
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U.S. Participation in the OEEC Halden Reactor Project May 1959 to September 1960
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Preliminary Design of a Basic Radiation Effects Reactor (BRER)
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Manufacture of Fuel Plates for the Experimental Boiling Water Reactor
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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.
Recrystallization in Rolled Uranium Sheet
No Description
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.
A Process for the Recovery of Uranium From Nuclear Fuel Elements Using Fluid-Bed Drying and Volatility Techniques
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Roll Cladding Uranium-Zirconium and Uranium-Zirconium-Niobium Alloys with Zircaloy-2 for Plate-Type Fuel Elements
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Hazards Summary Report on the Oxide Critical Experiments
Report describing a zero-power reactor facility (ZPR-VII), its systems, and associated hazards.
A Shielded Metallograph for Remote Metallography
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Summary Report on the Hazards of the Argonaut Reactor
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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).
Neutron Scattering Angular Distribution
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Operational Tests of EBWR Vapor Recovery System
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A Report on Some Attempts to Case Centrifugally Fuel Elements of Small Diameter
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