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Publications Received in the Library of the National Bureau of Standards, July 1962

Description: Report providing an alphabetical listing of the periodicals, both American and foreign, that are currently being received in the Washington (D.C.) Library of the National Bureau of Standards. Approximately 2,000 titles are cited, together with call numbers indicating the location of each in the NBS Washington Library. Although this information was compiled primarily for the use of the Bureau's scientific staff, it is also of value to libraries, scientific and technical organizations, and resear… more
Date: November 23, 1962
Creator: Hopper, Natalie J.
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Study of Requirements and Suitability of Available Reactors for Fast Fuel Tests

Description: Report issued by the APDA over studies conducted on the requirements of reactors for fuel testing. As stated in the summary, "the purpose of this study is to determine the requirements for radiation space for fast reactor fuel testing and to determine the capability of existing Commission and private test and power reactors to meet these requirements" (p. 7). This report includes tables, and illustrations.
Date: February 23, 1963
Creator: Doyle, T. A.; Duffy, J. G.; Jens, W. H.; McHugh, W. E.; Page, E. M. & Warberg, H. S.
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IBM 1401 Computer Produced and Maintained Library Circulation Records

Description: Report issued by the University of California Lawrence Radiation Laboratory discussing a method of updating library circulation records on an IBM 1401 computer. The report describes the methods of generating and updating the records using transaction cards to create computer tapes that are sorted and updated to prepare current reports of circulation information.
Date: January 23, 1964
Creator: Kennedy, James H.
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Report of the Forty-Seventh National Conference on Weights and Measures, 1962

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.
Date: November 23, 1962
Creator: United States. National Bureau of Standards.
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Effect of Explosive Impacting on Uranium

Description: Abstract: The tensile and yield strengths of both cast and wrought uranium discs were substantially increased by explosively impacting them at room temperature and at 375 deg F. However, the room-temperature impacting caused gross damage in the cast material and slight internal damage in the wrought material at the highest impacting pressures. Impacting at 375 deg F, which is just above the brittle-ductile transition temperature for uranium, was the most effective method for increasing the stre… more
Date: April 23, 1964
Creator: Burditt, R. B.; Carey, W. T. & Coughlen, C. P.
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients

Description: Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps

Description: Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept

Description: Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
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Reactor scram report for period of July 1, 1965--December 31, 1965

Description: The reactor scrams are summarized in a table which identifies the component.that opens the safety circuit and the reason or cause for the safety circuit trip. Caution should be exercised in the use of the summary for specific analysis of reactor scram causes. In a high percentage of cases, the component that opens the safety circuit is not at fault. A description of the reason or cause for a particular scram is given in the body of the report. The actual outage time charged to the cause of the … more
Date: February 23, 1966
Creator: Newell, L. J.
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Supplement to Reactor Containment Design Study

Description: Summary: Report SL-1868 is a technical and economic feasibility study of four containment methods, i.e., standard containment, pressure relief, pressure supression and low pressure containment, for 44 MWe direct cycle and 180 and 300 MWe dual cycle boiling water reactor plants.
Date: April 23, 1962
Creator: Johnson, R. A. & Nelson, I.
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The Sedan Event: On-Site Radiological Safety Report

Description: Summary: The on-site radiological support program for Project Sedan was established to assist in exclusion area control, to ninimize the radiation exposure of participating personnel and observers, and to prevent the spread of radioactive contamination.
Date: October 23, 1962
Creator: Reynolds Electrical & Engineering Co. Radiological Safety Division. Health Medicine, and Safety Department.
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Extruded Ceramic Nuclear Fuel Development Program. Final Report

Description: Urania rods 6-in. long and 0.475-in. in diameter were extruded and sintered to densities exceeding 94% of the theoratical urania density. The rods dropped freely through a straight metal tube 8-in. long with an internal diameter 0.004-in. greater than the diameter of the rods. All properties of the extruded and sintered rods relevant to their use as a nuclear fuel material were at least equal to the corresponding properties of pressed and sintered urania pellets. Extruded and sintered urania ro… more
Date: January 23, 1961
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