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  Partner: UNT Libraries Government Documents Department
 Resource Type: Report
 Collection: Technical Report Archive and Image Library
Standard X-ray Diffraction Powder Patterns: Section 18. Data for 58 Substances

Standard X-ray Diffraction Powder Patterns: Section 18. Data for 58 Substances

Date: October 1981
Creator: Morris, Marlene C.; McMurdie, Howard F.; Evans, Eloise H.; Paretzkin, Boris; Parker, Harry S.; Panagiotopoulos, Nicolas C. et al.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Summary of Available Data on the Strontium 90 Content of Foods and of Total Diets in the United States

Summary of Available Data on the Strontium 90 Content of Foods and of Total Diets in the United States

Date: August 18, 1960
Creator: Harley, John H. & Rivera, Joseph
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Ultramicro Methods in Biochemistry: [Part] 1. General Consideration, [Part] 2. Procedures for the Determination of Serum Bilirubin

Ultramicro Methods in Biochemistry: [Part] 1. General Consideration, [Part] 2. Procedures for the Determination of Serum Bilirubin

Date: October 1962
Creator: Van Stewart, E.; Puckett, Charles R. & Wood, Agnes
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements

Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements

Date: December 1959
Creator: Salley, R. L. & Burt, W. R., Jr.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Hazard Summary Report on the Experimental Boiling Water Reactor (EBWR)

Hazard Summary Report on the Experimental Boiling Water Reactor (EBWR)

Date: 1958
Creator: West, J. M.; Dietrich, J. R.; Jameson, A. S.; Anderson, G. A.; Harrer, J. M. & Brush, H. F.
Description: Report discussing possible hazards and preliminary safeguards for a 20-megawatt Experimental Boiling Water Reactor (EBWR) power plant
Contributing Partner: UNT Libraries Government Documents Department
Design of the Argonne Low Power Reactor (ALPR)

Design of the Argonne Low Power Reactor (ALPR)

Date: May 1961
Creator: Hamer, E. E.; Grant, N. R.; Hooker, H. H.; Jorgensen, G. L.; Kann, W. J.; Lipinski, W. C. et al.
Description: 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)
Contributing Partner: UNT Libraries Government Documents Department
Experimental Breeder Reactor-II (EBR-II) Shield Design

Experimental Breeder Reactor-II (EBR-II) Shield Design

Date: September 1962
Creator: Grotenhuis, M.; McArthy, A. E. & Rossin, A. D.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Dynamic Analysis of Coolant Circulation in Boiling Water Nuclear Reactors

Dynamic Analysis of Coolant Circulation in Boiling Water Nuclear Reactors

Date: April 1964
Creator: Sanathanan, Chathilingath K.
Description: 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)
Contributing Partner: UNT Libraries Government Documents Department
The Control of Condensation Heat Transfer Rates Using an Electromagnetic Field

The Control of Condensation Heat Transfer Rates Using an Electromagnetic Field

Date: July 1964
Creator: Singer, Ralph M.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle

An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle

Date: July 1963
Creator: Vogrin, Joseph A., Jr.
Description: 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).
Contributing Partner: UNT Libraries Government Documents Department
Development of an Electrical Resistivity Probe For Void-Fraction Measurements in Air-Water Flow

Development of an Electrical Resistivity Probe For Void-Fraction Measurements in Air-Water Flow

Date: June 1963
Creator: Nassos, George P.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
The Facility 350 Helium-Atmosphere System

The Facility 350 Helium-Atmosphere System

Date: December 1962
Creator: Mayfield, R. M.; Tope, W. G. & Shuck, A. B.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)

Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)

Date: April 1963
Creator: Hesson, J. C.; Feldman, M. J. & Burris, L.
Description: 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)
Contributing Partner: UNT Libraries Government Documents Department
Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat

Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat

Date: December 1963
Creator: Kramer, W. C. & Bean, C. H.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Design Summary Report on the Juggernaut Reactor

Design Summary Report on the Juggernaut Reactor

Date: September 1962
Creator: Folkrod, J. R.; Ember, G.; Kolb, W.; Saluja, J. & Moon, D. P.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
U.S. Participation in the OEEC Halden Reactor Project May 1959 to September 1960

U.S. Participation in the OEEC Halden Reactor Project May 1959 to September 1960

Date: December 1960
Creator: Fromm, Leonard W., Jr.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Design and Hazards Summary Report Boiling Reactor Experiment V (BORAX V)

Design and Hazards Summary Report Boiling Reactor Experiment V (BORAX V)

Date: May 1961
Creator: Argonne National Laboratory
Description: Report describing the design and usage of the BORAX V nuclear reactor, its surrounding facility, systems, experimental programs, and possible hazards.
Contributing Partner: UNT Libraries Government Documents Department
Hazard Evaluation Report on the Fast Reactor Zero Power Experiment ZPR-III

Hazard Evaluation Report on the Fast Reactor Zero Power Experiment ZPR-III

Date: October 1961
Creator: Long, J. K.; McVean, R. L.; Thalgott, F. W. & Novick, M.
Description: Report documenting the fast zero power reactor experiment (ZPRG-III). This includes a description of the experiment and the reactor, hazards, and accidents.
Contributing Partner: UNT Libraries Government Documents Department
Corrosion Studies of Ternary Zirconium Alloys in High-Temperature Water and Steam

Corrosion Studies of Ternary Zirconium Alloys in High-Temperature Water and Steam

Date: July 1961
Creator: Misch, R. D. & Van Drunen, C.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
EBR-II Dry Critical Experiments Experimental Program, Experimental Procedures, and Safety Considerations

EBR-II Dry Critical Experiments Experimental Program, Experimental Procedures, and Safety Considerations

Date: February 1961
Creator: Koch, L. J.; Loewenstein, W. B.; Lovoff, A.; Hooker, H. H.; Monson, H. O.; Ramp, R. L. et al.
Description: 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.)
Contributing Partner: UNT Libraries Government Documents Department
An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters

An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters

Date: October 1961
Creator: Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Hazards Summary Report on the Oxide Critical Experiments

Hazards Summary Report on the Oxide Critical Experiments

Date: April 1957
Creator: Redman, W. C.; Thie, J. A. & Dates, L. R.
Description: Report describing a zero-power reactor facility (ZPR-VII), its systems, and associated hazards.
Contributing Partner: UNT Libraries Government Documents Department
The Fabrication of Certain Jacketed Uranium Helices

The Fabrication of Certain Jacketed Uranium Helices

Date: May 1957
Creator: Yaggee, F. L.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Boiling Water Reactor Technology Status of the Art Report: Volume 1., Heat Transfer and Hydraulics

Boiling Water Reactor Technology Status of the Art Report: Volume 1., Heat Transfer and Hydraulics

Date: February 1962
Creator: Lottes, P. A.
Description: Report discussing state of the art design and operation of heat transfer and hydraulics equipment and technology in boiling water reactor power plants.
Contributing Partner: UNT Libraries Government Documents Department
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