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Modified Liquid Phase Reactor

Description: The following report describes a modified Kraus type reactor that had been constructed for use in bets chemical conversion operations.
Date: June 23, 1944
Creator: Zuidema, J. W. & Ballard, A. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aqueous Homogeneous Reactors for Producing Central-Station Power

Description: Report issued by the Oak Ridge National Laboratory discussing aqueous homogeneous reactors used in central-station power. As stated in the introduction, "it contains an evaluation of the potentiality of producing power only, as exhibited by aqueous homogeneous systems" (p. 6). This report includes tables, and illustrations.
Date: May 25, 1951
Creator: Briggs, R. B.; Haubenreich, P. N.; Sanders, J. P.; Aven, R. E.; Zapp, F. C.; Segaser, C. L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurement of distortion in second experimental control rod for argonne naval reactor with constant transverse temperature gradient and uniform longitudinal temperature distribution

Description: Report presenting measurements of the thermal distortion of a stainless-steel clad, cadmium-silver reactor control rod. The temperature pattern of the rod is described. The maximum reduction in clearance obtained in the tests was 0.203 inch.
Date: September 26, 1951
Creator: Nagey, T. F. & Lietzke, A. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurement of distortion in second experimental control rod with temperature patterns simulating shim rod out and shim rod 50 percent inserted for Argonne Naval Reactor

Description: Thermal distortion tests were made on a stainless steel clad, cadmium-silver control rod furnished by the Argonne National Laboratory. Two temperature patterns supplied by the Argonne National Laboratory were simulated in these tests; one represented the shim-rod-out condition and the other the shim-rod-50-percent-inserted condition. The greatest reduction in clearance effected by thermal distortion was 0.076 inch. No permanent set of the control rod was observed after repeated heating and cool… more
Date: September 26, 1951
Creator: Lietzke, A. F. & Nagey, T. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Sodium Hydroxide Reactor: Effect of Reactor Variables on Criticality and Fuel-Element Temperature Requirements for Subsonic and Supersonic Aircraft Nuclear Propulsion

Description: Report presenting results of two-group criticality calculations for sodium-hydroxide-cooled, moderated, and reflected reactors for various concentrations and compositions of reactor fuel-element structural material. Based on turbojet-engine cycle operating conditions optimized for minimum airplane gross weight, the maximum reactor fuel-element and coolant temperatures are related to the reactor heat release and airplane gross weight for a range of reactor heat-transfer variables.
Date: February 10, 1953
Creator: Bogart, Donald & Valerino, Michael F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium Graphite Reactor, Quarterly Progress Report, June-August 1953

Description: "Engineering was continued on the development of sodium cooled, graphite moderated type reactors. General studies were carried out as well as studies specifically devoted to the following: a. full scale poser-only plant, b. thirty-mega watt pilot plant, the SGR, c. sodium reactor experiment, the SRE. This work consisted of theoretical analysis of various aspects of nuclear performance; economic investigations of different fuel element, cooling system and plant arrangements; and experimental i… more
Date: January 20, 1954
Creator: Inman, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Engineering Division Quarterly Report: December 1, 1953 Through March 30, 1954

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: April 15, 1954
Creator: Argonne National Laboratory. Reactor Engineering Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LMFR-9 Static Corrosion Behavior of Materials in Bismuth and Uranium-Bismuth Solution at 550°C

Description: Report issued by the Brookhaven National Laboratory discussing corrosion behaviors of materials in bismuth. As stated in the introduction, "this report will present the details of the corrosion testing and the results obtained to date on materials tested under static conditions in bismuth media" (p. 1). This report includes tables, illustrations, and photographs.
Date: August 1954
Creator: Atherton, J. E.; Kammerer, O. F.; Klamut, C. J. & Sadofsky, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Operating Manual for the MTR, Section Two -- Exclusion Area, Materials Testing Reactor

Description: From summary: "This manual is designed for the purpose of clarifying operating procedures of the Materials Testing Reactor and its associated equipment. In assembling this manual a description of each item of equipment and its function is presented. In addition, the generally accepted method of operating the equipment and the best corrective measures concerning all emergencies that might be encountered are set forth herein. Descriptive drawings and written instructions pertaining to the equipme… more
Date: 1955
Creator: Phillips Petroleum Company. Atomic Energy Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Information Report by Atomic Power Development Associates Covering Work from the Period August 1, 1954 to January 31, 1955

Description: Report issued by the APDA over the work conducted between August 1954 and January 1955. Descriptions of the studies, facilities, and equipment used during this time are presented. This report includes tables, illustrations, and photographs.
Date: January 31, 1955
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemistry Division Semiannual Progress Report for Period Ending June 20, 1955

Description: Continued work on the adsorbability of metal complexes from concentrated LiCl solutions and LiCl-HCl mixtures on a strong-base anion-exchange resin further demonstrated the much higher adsorbability of these complexes from LiCl solutions than from HCl solutions. The effect is believed to be due to the formation of less strongly adsorbed undissociated chloro-complex acids in the case of the HCl solutions.
Date: June 20, 1955
Creator: Taylor, E. H. & Bredig, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transient Temperature Simulation of Reactor Primary Loop

Description: Report issued by the APDA over simulator studies conducted on their Developmental Fast Breeder Reactor. The simulator studies were "designed to predict both the normal and abnormal operating characteristics of the APDA Developmental Fast Breeder Reactor" (p. 1). This report includes tables, and illustrations.
Date: February 1, 1956
Creator: Olson, Richard G. & Ritchie, Donald J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bibliography of ORNL-BSF Reports Pertinent to Swimming Pool Type Reactor Design (Revised)

Description: Much of the shielding work carried out with the Bulk Shielding Reactor (BSR) has yielded data of particular interest for the design of swimming pool type reactors, However, it is often difficult for a reactor designer to locate such data since it may be recorded in a report primarily concerned with shielding problems. Therefore, this memorandum presents a bibliography of reports from the Bulk Shielding Facility arranged according to the application of data to the various aspects of reactor desi… more
Date: April 13, 1956
Creator: Maienschein, F. C. & Johnson, E. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary Hazards Report on Enriched Fuel Element Loading for the BNL Research Reactor

Description: Report issued by the Brookhaven National Laboratory discussing a hazards report on replacing the research center's current fuel elements with new highly enriched elements. As stated in the introduction, "this report is a summary of the studies, both theoretical and experimental, which have been made so far of the nuclear properties of the "new" pile, of the stability of the new fuel elements, and of the safety and practicability of operation of the "new" pile" (p. 2). This report includes table… more
Date: May 24, 1956
Creator: Corngold, N.; Kaplan, I.; Chernick, J.; Gurinsky, D. H. & Fowell, R. W.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: August-October 1956

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 19, 1957
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Bruce, F. R. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: November 1956-January 1957

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress of the Homogeneous Reactor Project. Progress of operations, design, development, and analysis is presented. This report includes tables, illustrations, and photographs.
Date: April 22, 1957
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Bruce, F. R. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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