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  Partner: UNT Libraries Government Documents Department
 Decade: 1950-1959
 Collection: Technical Report Archive and Image Library
Report of the Forty-Fourth National Conference on Weights and Measures, 1959

Report of the Forty-Fourth National Conference on Weights and Measures, 1959

Date: December 18, 1959
Creator: United States. National Bureau of Standards.
Description: Report of the annual conference on weights and measures, hosted by the U.S. National Bureau of Standards in Washington D.C. It includes conference proceedings, a list of attendees, information about committees and officers, and other reports or commentaries discussed at the meetings.
Contributing Partner: UNT Libraries Government Documents Department
Metallurgy Division Annual Progress Report, September 1, 1959

Metallurgy Division Annual Progress Report, September 1, 1959

Date: December 16, 1959
Creator: Oak Ridge National Laboratory. Metallurgy Division.
Description: Report documenting ongoing research and development undertaken by the Metallurgy Division of the Oak Ridge National Laboratory.
Contributing Partner: UNT Libraries Government Documents Department
Hazards Analysis of the Organic Moderated Reactor Experiment

Hazards Analysis of the Organic Moderated Reactor Experiment

Date: December 15, 1959
Creator: Williams, R. O. & Allen, W. O.
Description: Introduction: The description of the Organic Moderated Reactor Experiment, (OMRE), its location, its safety system, and operative procedures have been previously detailed. The present report, although dealing with the subject of OMRE safety, has the more detailed intent of (1) determining the behavior of the OMRE under extremely unlikely sets of conditions; and (2) providing additional design information in the areas of reactivity coefficients, burnout heat flux, and reactor control.
Contributing Partner: UNT Libraries Government Documents Department
Power Flattening in Sodium Graphite Reactors by Spatial Variation of Moderator Properties

Power Flattening in Sodium Graphite Reactors by Spatial Variation of Moderator Properties

Date: December 15, 1959
Creator: Connolly, T. J.
Description: Abstract: In the present study, the variation of moderator composition was postulated to be effected by the inclusion of varying amounts of beryllium oxide in the graphite of an SGR.
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
Experimental Organic Cooled Reactor : Conceptual Design

Experimental Organic Cooled Reactor : Conceptual Design

Date: December 1, 1959
Creator: Huffman, John R.; Nyer, W. E. & Rainwater, J. H.
Description: Report presenting the design, research programs, and design objectives for an Organic-Cooled Reactor.
Contributing Partner: UNT Libraries Government Documents Department
Hazards Evaluation Report Associated With the Operation of EBWR at 100 MW

Hazards Evaluation Report Associated With the Operation of EBWR at 100 MW

Date: December 1959
Creator: Wimunc, E. A. & Harrer, J. M.
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: 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."
Contributing Partner: UNT Libraries Government Documents Department
Liquid Metal Fuel Reactor Experiment, Cavitation by Bismuth

Liquid Metal Fuel Reactor Experiment, Cavitation by Bismuth

Date: December 1959
Creator: Hovanec, F. L.
Description: From abstract: "Croloy 2 - 1/4 was tested to determine the causes and effects of cavitation in dynamic liquid bismuth solutions."
Contributing Partner: UNT Libraries Government Documents Department
Nuclear Superheat Quarterly Project Report: First Quarter, July-September 1959

Nuclear Superheat Quarterly Project Report: First Quarter, July-September 1959

Date: December 1, 1959
Creator: U.S. Atomic Energy Commission
Description: From introduction: "The purpose of the report is to set forth the development philosophy, objectives and expected results of the AEC-GE Nuclear Superheat Project."
Contributing Partner: UNT Libraries Government Documents Department
Operation of Pilot Plant LTV Evaporator at Wrightsville Beach, North Carolina

Operation of Pilot Plant LTV Evaporator at Wrightsville Beach, North Carolina

Date: December 1959
Creator: W. L. Badger and Associates, Inc.
Description: From Introduction: "The primary objective in the development of the W. L. Badger Long Tube Vertical Multiple Effect Evaporator for saline water conversion is to minimize the ultimate cost of producing potable water. To accomplish the primary objective, it is necessary to (1) prevent formation of scale on heating surfaces, and (2) minimize corrosion to permit use of inexpensive materials of construction. The work done leading to this report was guided in the direction of accomplishing the two secondary objectives."
Contributing Partner: UNT Libraries Government Documents Department
Preliminary Test of Natural-Circulation Double-Tube Steam Generator

Preliminary Test of Natural-Circulation Double-Tube Steam Generator

Date: December 1, 1959
Creator: Welsh, R. D.
Description: Abstract: Testing of the Natural Circulation Steam Generator has been conducted with the Sodium Reactor Experiment. A necessary modification of the original feed-water control system was utilized.
Contributing Partner: UNT Libraries Government Documents Department
Reactor Technology Report Number 11: Physics

Reactor Technology Report Number 11: Physics

Date: December 1959
Creator: unknown
Description: Quarterly report issued by the Knolls Atomic Power Laboratory to report to the industry on developments in unclassified reactor technology. This issue focuses on physics information.
Contributing Partner: UNT Libraries Government Documents Department
Performance of a Single Fuel-vaporizing Combustor With Six Injectors Adapted for Gaseous Hydrogen

Performance of a Single Fuel-vaporizing Combustor With Six Injectors Adapted for Gaseous Hydrogen

Date: November 30, 1959
Creator: Smith, A. L. & Wear, J. D.
Description: Single fuel-vaporizing combustor with injectors adapted for gaseous hydrogen.
Contributing Partner: UNT Libraries Government Documents Department
SRE Fuel Element Damage: An Interim Report

SRE Fuel Element Damage: An Interim Report

Date: November 30, 1959
Creator: Jarrett, A. A.
Description: Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Contributing Partner: UNT Libraries Government Documents Department
Hot-Pressure Bonding of OMR Fuel Plates

Hot-Pressure Bonding of OMR Fuel Plates

Date: November 15, 1959
Creator: Alm, G. V.; Binstock, M. H. & Garrett, E. E.
Description: Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Contributing Partner: UNT Libraries Government Documents Department
Terminal Status Report for the Processing Refabrication Experiment

Terminal Status Report for the Processing Refabrication Experiment

Date: November 15, 1959
Creator: Sinizer, D. I.; Mattern, K. L. & Kendall, E. G.
Description: Introduction: A low-capacity, low-decontamination plant can be built, as part of a power reactor complex, to avoid long distance transfer of fuel to a high-capacity aqueous processing plant. Activation of such a complex, with the processing plant adjacent to the reactor it serves, could decrease the cost of the integrated fuel cycle. The study of this concept is a major objective of the Processing Refabrication Experiment (PRE).
Contributing Partner: UNT Libraries Government Documents Department
Tory II-A: A Nuclear Ramjet Test Reactor

Tory II-A: A Nuclear Ramjet Test Reactor

Date: November 4, 1959
Creator: Hadley, James W.
Description: Report containing information regarding the design of the Tory II-A nuclear ramjet engine, and descriptions of its locale, test program, and possible hazards.
Contributing Partner: UNT Libraries Government Documents Department
Further Investigations of Natural Environmental Radiation

Further Investigations of Natural Environmental Radiation

Date: November 3, 1959
Creator: Solon, Leonard R.; Lowder, Wayne M.; Shambon, Arthur & Blatz, Hanson
Description: Report documenting the investigation of cosmic and terrestrial background radiation. "Remeasurements in many locations furnished estimates of dosimetric increase in terrestrial levels due to fallout. Radiation measurement sin residential dwellings in he New York metropolitan areas are described" (p. 1).
Contributing Partner: UNT Libraries Government Documents Department
Nuclear Safety in Manufacturing Plants

Nuclear Safety in Manufacturing Plants

Date: November 3, 1959
Creator: McLaughlin, James E.
Description: From Introduction: "In the following pages are summarized the factors which influence neutron economy and which, therefore, are important in nuclear safety."
Contributing Partner: UNT Libraries Government Documents Department
Nuclear Superheat Meeting: September 1959

Nuclear Superheat Meeting: September 1959

Date: November 3, 1959
Creator: unknown
Description: From introduction: The Commission's underlying objective of this program is to conduct sufficient engineering and development work to determine the most feasible and economical methods of producing nuclear super-heated steam from a boiling water reactor.
Contributing Partner: UNT Libraries Government Documents Department
Instrumentation and Controls Division Annual Progress Report, July 1, 1959

Instrumentation and Controls Division Annual Progress Report, July 1, 1959

Date: November 2, 1959
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
Description: Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.
Contributing Partner: UNT Libraries Government Documents Department
Advanced Designs of Magnetic Jack-Type Control Rod Drive

Advanced Designs of Magnetic Jack-Type Control Rod Drive

Date: November 1959
Creator: Young, Joseph N.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
ANPP Code Development Program Pressurized Water Task Quarterly Progress Report: Number One, November 1959

ANPP Code Development Program Pressurized Water Task Quarterly Progress Report: Number One, November 1959

Date: November 1959
Creator: Olsen, T. M.; Welshans, L. & Eicheldinger, C.
Description: From introduction: The objective of this program is the development of a nuclear physical model and its calculation code for pressurized-water cooled and moderated reactors to predict accurately reactivity, rod positions and power distributions at operating temperatures, and reactor life from a nuclear standpoint.
Contributing Partner: UNT Libraries Government Documents Department
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