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Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1963 - September 1, 1963

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: October 1, 1963
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
Partner: UNT Libraries Government Documents Department
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The Stage Constants of Cascade Impactors

Description: From Introduction: "In the present work, the relationship between the true MMD's calculated in this way and the MMD's which could be obtained from a microscope analysis has been determined. This has been done to establish that the comparison being made gives a valid representation of what could be encountered in practice. The comparison has then been extended to cover a wide range of particle size distributions for three different impactors."
Date: October 1963
Creator: Mercer, T. T.
Partner: UNT Libraries Government Documents Department
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A Performance Analysis of the EBWR at Various Power Levels

Description: From Introduction: "This study is an attempt to predict the operating performance of EBWR (Experimental Boiling Water Reactor) at various power levels. It was done at the same time that EWBR was raised in power up to 100 MW, and so an excellent possibility was given to check the validity of the used performance analysis. Rather than giving a general and complete outline of the analysis or establishing a new approach, the study outlines and specifies the numerous practical problems involved in this analysis, and tries to explain the discrepancies between predicted and experimental results."
Date: October 1963
Creator: Nentwich, Alfred A.
Partner: UNT Libraries Government Documents Department
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Compilation of the Melting Points of the Metal Oxides

Description: Report compiling the melting points of 70 metal oxides published prior to January 1963. Both the original melting point and the equivalent value based on the International Practical Temperature Scale of 1948 are presented. Included in the survey is information on pertinent experimental details such as the method of temperature measurement, purity, furnace type, and environmental conditions.
Date: October 10, 1963
Creator: Schneider, Samuel J.
Partner: UNT Libraries Government Documents Department
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Final Summary Report of the Gas-Cooled Reactor Experiment-1

Description: Report describing the Gas-Cooled Reactor test facility, its ongoing testing and evaluations of a test reactor, and its operating conditions and characteristics.
Date: October 1963
Creator: Chesworth, R. H.
Partner: UNT Libraries Government Documents Department
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Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor

Description: Report containing the description and design of U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor. Topics include the requirements of core materials, materials specifications, manufacturing procedures, and shipping preparation.
Date: October 21, 1963
Creator: Kucera, W. J.; Leitten, C. F., Jr. & Beaver, R. J.
Partner: UNT Libraries Government Documents Department
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Fundamentals in the Operation of Nuclear Test Reactors: Volume 2, Materials Testing Reactor Design and Operation

Description: Second volume of reports on the operation of nuclear test reactors. It includes six chapters: engineering description fo the materials testing reactor, reactor control components and instrumentation, reactor control circuitry, reactor operation, reactor shutdown and tank work, and supplemental facilities at the materials testing reactor.
Date: October 1963
Creator: Phillips Petroleum Company
Partner: UNT Libraries Government Documents Department
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Investigation of impulsively loaded pressure vessels

Description: Explosion containment vessels for containing from 2,000 to 3,000 five ton nuclear explosions are considered. Analysis methods appear adequate and lowest weights using the most advanced materials available in the next five years are projected.None of these materials can be fabricated today and all require extensive development. Present material technology limits the choice of materials and defines the weight. The addition of safety factors and fixtures (nozzles, etc.) will add to this weight considerably, and may well radically alter the vessel response. Improvements in the strength weight ratios of metals and glasses over those considered in this report do not appear reasonable at this time. Winding schemes to utilize the high strength of steel wires and somehow maintain a reasonable thickness appear to offer the most promise. A `ductile` beryllium would of course offer vast improvement, but no indications that this is being developed have appeared and all presently known beryllium is much too brittle.
Date: October 15, 1963
Creator: Brown, N.; Cornwell, R.; Hanner, D.; Leichter, H. & Mohr, P.
Partner: UNT Libraries Government Documents Department
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STUDIES IN CONTACT MICRORADIOGRAPHY

Description: Recent developments in techniques for low-voltage radiography have found application for the examination and evaluation of minute details in small or thin specimens. Utilization of x-ray tubes and helium chambers with thin windows for maximum transmission of soft x rays and bare film with dark-room exposure techniques have allowed very high contrast radiographs to be produced on low-contrast materials. These conditions, coupled with very high resolution photographic emulsion detectors, have resulted in the observation of detail approximately 1 {micron} in size. Useful examination of the plates and subsequent reproductions have been made at magnifications as high as 500X. This contact system offers the advantage of evaluation of a relatively large area, as compared to the restricted field of observation of projection microradiography. Included among the subjects have been graphite-coated UC{sub 2} particles, graphite, beryllium, paper, and other organic specimens.
Date: October 16, 1963
Creator: McClung, R. W.
Partner: UNT Libraries Government Documents Department
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Aerospace Nuclear Safety: October 1 - 4, 1963

Description: Proceedings on aerospace nuclear safety.
Date: October 1963
Creator: Sandia Corporation. Technical Information Division III.
Partner: UNT Libraries Government Documents Department
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Secondary Missiles Generated by Nuclear-Produced Blast Waves

Description: Report from Operation Plumbob regarding an experiment investigating secondary missiles created by blast waves from nuclear detonations of three different yeilds.
Date: October 28, 1963
Creator: Bowen, I. Gerald; Franklin, Mary E.; Fletcher, E. Royce & Albright, Ray W.
Partner: UNT Libraries Government Documents Department
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A Photographic Study of Boiling Flow

Description: From abstract: A high speed motion picture study was conducted of boiling flow in a vertical, rectangular channel at atmospheric pressure. Three different visual flow regimes were defined and described.
Date: October 25, 1963
Creator: Vohr, John Henry
Partner: UNT Libraries Government Documents Department
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Project Scooter: Final Report, October 1963

Description: From abstract: This report includes results of studies of crater dimension, throwout material distribution, ground motion, dust cloud growth, and long-range air blast.
Date: October 1963
Creator: Perret, William R.; Chabai, Albert J.; Reed, Jack W. & Vortman, Luke J.
Partner: UNT Libraries Government Documents Department
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Chloride Deposition From Steam Onto Superheater Fuel Clad Materials

Description: Experimemts using Cl/sup 36/ in a steam test loop were conducted to study the deposition behavior of chlorides on BONUS superheater fuel assembly materials. The moisture content of the steam was varied between 0 and 0.5 wt%, and superheat was added up to 15 deg F before the steam passed over the test cartridge heater. The effects of vaiiables on the chloride deposition on the heater were studied in detail. Chloride deposition from moist steam was found to result in heavy, adherent deposits which are conducive to severe chloride stress corrosion of austenitic steels, while removal of all moisture from the incoming steam reduces the chloride deposition and minimizes the chloride stress corrosion. The heater surface condition was found to be a very important variable; deposition is increased by surface defects and pits. Neither the temperature of steam or heater nor the amount of superheat had an appreciable effect on the deposition, when no moisture existed in the steam. However, low steam velocities and spacer protoberances increase the deposition. Different clad materials (Inconel and Type 304 and 347 stainless steel) with similar surface conditions did not affect the deposition, although subsequent corrosion effects do modify the deposition behavior. Recommendations are given for the control of chloride deposition in nuclear superheater reactor systems. (D.L.C.)
Date: October 18, 1963
Creator: Bevilacqua, F. & Brown, G. M.
Partner: UNT Libraries Government Documents Department
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