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  Partner: UNT Libraries Government Documents Department
 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
Thermal Conductivity of Solids At Room Temperature and Below: A Review and Compilation of the Literature

Thermal Conductivity of Solids At Room Temperature and Below: A Review and Compilation of the Literature

Date: September 1973
Creator: Childs, Gregg E.; Ericks, Lewis J. & Powell, Robert L.
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
Terminal Report on the Mighty Mouse High-Flux Research Reactor Project

Terminal Report on the Mighty Mouse High-Flux Research Reactor Project

Date: September 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Dickson, R. F.; Heineman, J. B.; Kelber, C. N. et al.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Initial Testing and Operation of the Argonne Low Power Reactor (ALPR)

Initial Testing and Operation of the Argonne Low Power Reactor (ALPR)

Date: December 1959
Creator: Hamer, Eberhard E.
Description: None
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
Preliminary Design and Hazards Report-Boiling Reactor Experiment V (BORAX V)

Preliminary Design and Hazards Report-Boiling Reactor Experiment V (BORAX V)

Date: February 1960
Creator: Argonne National Laboratory
Description: None
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
Preliminary Physics and Heat Transfer Design Calculations for a Rocket Fuel Test Reactor (RFTR)

Preliminary Physics and Heat Transfer Design Calculations for a Rocket Fuel Test Reactor (RFTR)

Date: August 1964
Creator: MacFarlane, D. R. & Madell, J. T.
Description: None
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
Two-Phase Critical Flow With Application to Liquid-Metal Systems (Mercury, Cesium, Rubidium, Potassium, Sodium, and Lithium)

Two-Phase Critical Flow With Application to Liquid-Metal Systems (Mercury, Cesium, Rubidium, Potassium, Sodium, and Lithium)

Date: October 1963
Creator: Fauske, Hans K.
Description: None
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 Period Effect in Reactor Dynamics

The Period Effect in Reactor Dynamics

Date: April 1964
Creator: Carter, Joseph C.; Sparks, David W. & Tessier, Jack H.
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
Optimization of Efficiency of a Cesium Diode Converter

Optimization of Efficiency of a Cesium Diode Converter

Date: March 1962
Creator: Sanathanan, C. K.
Description: None
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
Proceedings of the AMU-ANL Summer Study Program

Proceedings of the AMU-ANL Summer Study Program

Date: November 1962
Creator: Pearson, C. V.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
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