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Progress Relating to Civilian Applications During July, 1956

Description: A report based on a study about the factors which affect the amount of chemical reaction between water and Zircaloy 2 at high temperatures. Also, experimental programs for the measurement of radiation emissivity, chemical reaction rates, and diffusion rates have been completed.
Date: August 1, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During July, 1957

Description: A report about equipment which is assembled and tested to determine the feasibility of measuring the thermal conductivity and electrical resistivity of irradiated uranium rods clad with Zircaloy 2 with NaK as the heat-transfer medium.
Date: August 1, 1957
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During July, 1958

Description: A report dealing with thermal-conductivity measurements of uranium and UO2 to determine the effect of irradiation on both of these two materials.
Date: August 1, 1958
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Partner: UNT Libraries Government Documents Department
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Final Safeguards Summary Report for the Piqua Nuclear Power Facility

Description: Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.
Date: August 1, 1961
Partner: UNT Libraries Government Documents Department
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300,000-KWE SGR Nuclear Power Plant of Current Technology

Description: Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
Date: August 1, 1960
Creator: Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
Partner: UNT Libraries Government Documents Department
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UC Fuel Element Design and Fabrication

Description: Abstract: Uranium monocarbide shows considerable potential for use as a fuel in high temperature, high power density, nuclear power reactors. As Atomics International is proposing its use in sodium graphite type reactors, it was necessary to develop a process for fabricaing sodium bonded uranium carbide fuel elements.
Date: August 1, 1964
Creator: Draganchuk, W.
Partner: UNT Libraries Government Documents Department
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Boiling Depressurization Transients

Description: Abstract: An analytical and experimental effort toward a better understanding of the mechanisms involved in nuclear power reactor loss-of-pressure accidents is presented.
Date: August 1, 1964
Creator: Halfen, F. J. & Berganzoli, F.
Partner: UNT Libraries Government Documents Department
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Thermal Stress Testing of Beryllium Oxide Moderator Shapes

Description: Abstract: Perforated BeO plates were thermal shock tested to evaluate the effect of: (1) localized temperature variations adjacent to the perforations, and (2) radial gradients across the entire plate.
Date: August 1, 1962
Creator: Sujata, H. L.; King, M. & Waters, F. J.
Partner: UNT Libraries Government Documents Department
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Uranium Carbide Transient Heating Experiments - Phase 1

Description: Abstract: Two in-pile capsules containing mock-up uranium carbide fuel rods were subjected to a total of five neutron bursts in the TREAT facility with initial reactor periods ranging from 0.26 to 0.10 sec.
Date: August 1, 1964
Creator: Stachura, S. J.; Silberberg, M. & Cordy, R. N.
Partner: UNT Libraries Government Documents Department
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Quarterly Report May 1947 to August 1947 : Biology Division

Description: The following documents were compiled into a quarterly report that was to be published in the Radiobiology Volume of the PPR. The following reports provide data from the Biology department of the University of Chicago between May and August of 1947.
Date: August 1, 1947
Creator: Brues, Austin M.
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor Shield Design Summary Report

Description: Abstract: "Most of the Nuclear Merchant Ship Reactor (NMSR) shield design work performed by The Babcock & Wilcox Company (B&W) is summarized. Primary and secondary shield results are presented, consistent with contractual requirements and designated design criteria. Methods of calculation and basic parameters are shown" (p. 1).
Date: August 1, 1959
Creator: Smith, W. R. & Turner, M. A.
Partner: UNT Libraries Government Documents Department
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High Temperature Liquid Metal Circulating System

Description: Introduction: The purpose of this experiment was to demonstrate that a liquid metal heat transfer system could be built and operated at very high temperatures.
Date: August 1, 1954
Creator: Keen, R. D.
Partner: UNT Libraries Government Documents Department
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Experimental Gas Cooled Reactor, Final Hazards Summary Report: Volume 2, Plant Operation

Description: From introduction: The information provided in Volume II describes programs, requirements, and procedures established by the Operator to minimize the probability of equipment failure, actions taken during any emergency to minimize radiation exposure dose to the general public and to plant personnel, and actions taken following a hazardous condition to prevent its recurrence.
Date: August 1, 1963
Partner: UNT Libraries Government Documents Department
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An Investigation of the Chattanooga Black Shale of Tennessee as a Source of Uranium Progress Report: July 1, 1956-June 30, 1957

Description: From introduction: The primary aim of this study is to present as complete a geologic picture as possible, of the Chattanooga shale in its outcrop area of the Eastern Highland Rim and the Northern Highland Rim of Tennessee and adjacent Kentucky. Special emphasis has been placed upon the stratigraphic relationships and their implications upon the age and manner of origin of the sediments and upon the origin, source, and distribution of uranium in the shale.
Date: August 1, 1957
Creator: Klepser, Harry J.
Partner: UNT Libraries Government Documents Department
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Underground Movement of Radioactive Wastes

Description: The theory and preliminary laboratory investigations presented in this technical report were intended to examine the general feasibility of injection disposal of radioactive wastes and to establish an understanding of the phenomena governing the travel of trace chemicals through natural porous media. Detailed studies of fluid velocity variations resulting from density differences between the injected and displaced liquids have been made. the ion exchange studies have been limited to strontium a… more
Date: August 1, 1955
Creator: Kaufman, Warren J., 1922-; Orcutt, Richard G., 1924- & Klein, Gerhard, 1918-1987
Partner: UNT Libraries Government Documents Department
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A Study of the Delayed Neutron Emitter, Br87

Description: Report discussing a study to determine experimentally whether a low neutron binding energy must be assigned to Kr⁸⁷ to explain the neutron emission or whether the beta-decay energy is especially high, as well as to determine the fission yield of Br⁸⁷.
Date: August 1, 1950
Creator: Stehney, Andrew Frank
Partner: UNT Libraries Government Documents Department
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Tentative Specification for Waste Heat Steam Boiler

Description: Report discussing specifications for the design of a waste heat steam boiler "for the purpose of generating steam to operate a condensing steam turbine electric generator from the clean hot radioactive air that has cooled the atomic energy reactor of [a] laboratory under a pressure less than atmospheric."
Date: August 1, 1948
Creator: Williams, C.
Partner: UNT Libraries Government Documents Department
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The Preparation of Uranyl Carbonate and Measurement of Its Solubility

Description: From summary: "A method for the preparation of normal uranyl carbonate has been developed. Heretofore, this compound has been known only as a rare, naturally occurring material." The report further discusses the physical properties of the compound, its solubility in water, and its interaction with sodium carbonate.
Date: August 1, 1949
Creator: Miller, P. D.; Pray, H. A. & Munger, H. P.
Partner: UNT Libraries Government Documents Department
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Properties of Tin Oxide: Base Ceramics

Description: From summary: "Various thermal and mechanical properties were measured for sintered tin oxide-matrix compacts which nominally were composed of 99 per cent by weight of tin oxide, SnO2, and one per cent by weight of zinc oxide ZnO...The tin oxide body might be expected to give good service under conditions of severe thermal shock and in an oxidizing atmosphere at temperatures up to 1500°F."
Date: August 1, 1951
Creator: Quirk, John F. & Herman, C. G.
Partner: UNT Libraries Government Documents Department
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Summary Report for April, May and June, 1951

Description: Report discussing progress made by the Chemistry Division (Section C-1) of the Argonne National Laboratory for the months of April, May and June, 1951. Information is divided into "Nuclear Chemistry and Radiochemistry" and "Basic Chemistry".
Date: August 1, 1951
Creator: Manning, W. M. & Osborne, D. W.
Partner: UNT Libraries Government Documents Department
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A Simplified Description of Spherical and Cylindrical Blast Waves

Description: "Investigations into the behavior of the gas flow behind spherical or cylindrical blasts have shown that secondary shocks arise within the original detonation gases. The secondary shock, at first weak, is carried outward with the expanding gases. Subsequently it strengthens and bends back toward the origin, arriving there with high intensity. By using some recently developed techniques in shock dynamics a theory is developed by which the motion of the main shock wave, as well as the formatio… more
Date: August 1, 1960
Creator: Friedman, M. P.
Partner: UNT Libraries Government Documents Department
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The Use and Calibration of Scintillation Counter--Model Y

Description: Several improvements have been made in the gamma scintillation counter (GSC). The Model V gamma scintillation counter uses a canned thallium activated sodium iodide crystal as a detector. Although the electronic components remain unchanged, a modification of the sample support has been made to improve reproducibility of geometry. To assure comparable results between various counters, they must be operated at the same energy threshold and counting yield. Methods have been developed to assure… more
Date: August 1, 1953
Creator: Brauer, F. P. & Leboeuf, M. B.
Partner: UNT Libraries Government Documents Department
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Maritime Loop Irradiation Program, S-I-5-B-M Fuel Irradiation Water Chemistry, Final Report

Description: Introduction: The purpose of this technical report is to review the water chemistry methods and equipment developed for use with the Maritime Loop Irradiation Program conducted in the General Electric Test Reactor (GETR) from December 2, 1960 to July 19, 1962. Special emphasis is given to areas having general application to other high purity water systems. The Appendix includes a discussion of specific conductivity and pH in high purity water systems. A major section of this report is devoted t… more
Date: August 1, 1963
Creator: Danielson, D. W.; Gilbert, R. S. & Panter, G. E.
Partner: UNT Libraries Government Documents Department
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