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Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office

Description: Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Partner: UNT Libraries Government Documents Department
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Savannah River Project Site Report: 30,000 KW Prototype Partically Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission Idaho Operations Office

Description: Report describing a modified prototype of a nuclear reactor that uses partially uranium-enriched fuel and is cooled by helium. The construction site, site safety aspects, and design and construction costs are included.
Date: March 1959
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Partner: UNT Libraries Government Documents Department
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Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959

Description: Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
Date: May 25, 1959
Creator: Aerojet-General Corporation
Partner: UNT Libraries Government Documents Department
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Ceramic Investigations of UO₂

Description: This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
Date: June 16, 1955
Creator: Allison, Adrian G. & Duckworth, Winston H.
Partner: UNT Libraries Government Documents Department
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Hot-Pressure Bonding of OMR Fuel Plates

Description: Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date: November 15, 1959
Creator: Alm, G. V.; Binstock, M. H. & Garrett, E. E.
Partner: UNT Libraries Government Documents Department
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Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO

Description: Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects.
Date: August 23, 1956
Creator: Andelin, Robert L.; Anderson, Edward L. & McVey, W. H.
Partner: UNT Libraries Government Documents Department
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Materials Testing Reactor Project Handbook

Description: The following handbook was made for the purpose of: (1) to give a semidetailed description of the testing reactor, and (2) to explain, in so far as possible, the reasons for the design.
Date: May 7, 1951
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
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Li⁶ and Li⁷ (n. 2n) Cross Sections at 14.1 Mev

Description: Abstract: "An absolute measurement of the 14.1-Mev (n, 2n) cross sections of Li-6 and Li-7 has been made using the large scintillator technique, resulting in cross sections in barns of 0.070 +/- 0.006 and 0.056 +/- 0.005 for Li-6 and Li-7, respectively."
Date: May 29, 1958
Creator: Ashby, V. J.; Catron, H. C.; Newkirk, Lester L.; Taylor, C. J. & Williamson, M. A.
Partner: UNT Libraries Government Documents Department
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An Evaluation of the Calder Hall Type of Nuclear Power Plant

Description: Abstract: Presented herein is the preliminary design of a natural uranium, graphite moderated, CO2-cooled reactor and power plant similar to, but larger than, the British Calder Hall plant, with a net electrical output of 130 MWE.
Date: January 18, 1957
Creator: Banks, William F.; Schneider, G. A.; Morgan, William T. & Ash, E. B.
Partner: UNT Libraries Government Documents Department
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Electroplated Metals on Uranium for Aluminum Cladding

Description: Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outgassing of the nickel-plated uranium prior to aluminum cladding were beneficial, and minimizing the amount of air present in the hot-press assembly was desirable. Variation in the steps for electroplating on uranium did not affect the corrosion resistance of aluminum-clad uranium."
Date: May 4, 1955
Creator: Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
Partner: UNT Libraries Government Documents Department
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The Elimination of Microwave Reflections

Description: Abstract: "The reflections of microwaves from the walls of a plasma-containing vessel are studied. The probable cause of the reflections is discussed, and several suggestions are made for eliminating the reflections from the waveguide in the vessel and particularly from the pyrex vessel wall and copper tubing surrounding the pyrex. Quarter-wave-thick carbon-filled plastics or glasses having a very low vapor pressure room most promising when placed inside the pyrex cylinder. BaTiO3 appears to be an excellent material when placed outside the vacuum."
Date: February 1, 1955
Creator: Beard, David
Partner: UNT Libraries Government Documents Department
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The Shielding of Mobile Reactors - [Part] 2

Description: From abstract: "The methods of applying results of bulk-shielding measurements to the design of reactor shields is outlined. Geometrical transformations for the more common shapes are derived, as are approximate means of calculating leakage of radiation. As an illustration of the methods, the ORNL Lid Tanks and Bulk Shielding Facility data are transformed to a standard geometry and compared. Two direct calculations of water attenuation, using cross sections described in the previous article, are finally compared with the experimental data."
Date: June 30, 1952
Creator: Blizard, E. P. & Welton, T. A.
Partner: UNT Libraries Government Documents Department
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Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956

Description: Report issued by the Oak Ridge National Laboratory discussing work completed by the Applied Nuclear Physics Division during 1956. Summaries of experiments conducted and project developments are presented. This report includes tables, illustrations, and photographs.
Date: November 20, 1958
Creator: Blizard, E. P.; Simon, A.; Callihan, A. D.; Clifford, C. E.; Maienschein, F. C. & Peelle, R. W.
Partner: UNT Libraries Government Documents Department
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Carbide Fuel Development: Phase 1 Report, Period of May 15 to September 15, 1959

Description: From foreword: This report describes the work accomplished including the Conceptual Design task and the initial results of the tasks on Facility Design and Fabrication, Fuel Fabrication and Evaluation, and Fuel Reprocessing.
Date: October 15, 1959
Creator: Bolomey, R.; Lazerus, S.; Sapir, J.; Sofer, G.; Steinmetz, H.; Strasser, A. et al.
Partner: UNT Libraries Government Documents Department
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Instrumentation and Controls Division Semiannual Progress Report for Period Ending July 31, 1956

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Instrumentation and Controls Division. Descriptions of progress and studies conducted are presented. This report includes illustrations, and photographs.
Date: February 25, 1957
Creator: Borkowski, C. J.
Partner: UNT Libraries Government Documents Department
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Initial Measurements on the Angular Distribution of Deuterium Plasma Produced by a Pulsed Spark Source

Description: Abstract: "The deuterium plasma which is ejected by a 6000-ampere pulsed current through a rail-type spark source has a yield in the forward direction which is a factor of 5 to 10 greater than that in the perpendicular direction. This effect is believed to be due to the magnetic propulsion of the plasma."
Date: March 24, 1955
Creator: Bostick, W. H.
Partner: UNT Libraries Government Documents Department
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