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Reactor Development Program Progress Report

Description: Research and development activities are reported on EBWR, BORAX-V, ZPR- III, ZPR-VI, ZPR-IX, EBR-I, and EBR-II. Thermal- and fast-reactor safety studies are summarized. Applied nuclear and reactor physics, reactor fuels development, reactor materials development, reactor components development, heat engineering, separations processes, and advanced reactor development are discussed. (M.C.G.)
Date: March 1, 1961
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report

Description: Progress on reactor programs and in general engineering research and development programs is summarized. Research and development are reported on water-cooled reactors including EBWR and Borax-V, sodium-cooled reactors including ZPR-III, IV, and IX, Juggernaut, and EBR-I and II. Other work included a review of fast reactor technology, and studies on nuclear superheat, thermal and fast reactor safety, and reactor physics. Effort was also devoted to reactor materials and fuels development, heat e… more
Date: April 1, 1961
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report, February 1961

Description: Design, development, and testing efforts were continued on BORAX-V, EBR- I, EBR-II, EBWR, JUGGERNAUT ZPRIII, ZPR-VI, and ZPR-W. An evaluation program is outlined for Pebble Bed Reactor designs. Fast and thermal reactor safety studies were conducted. Experimental and theoretical studies in applied nuclear and reactor physics are dsscribed. Developments made in reactor components, fuels, and materials are discussed. Heat engineering studies were conducted on steam separation, and velocity and voi… more
Date: March 15, 1961
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report, January 1961

Description: Modifications of EBWR are described, and data from analysis of control- rod operational crud deposit are tabulated. Development and construction progress on Borax V are summarized. Research for ZPR III is reported on a series of uranium oxide critical cores. Comparative data on composition, critical masses, and central fission ratios are tabulated for these assemblies. Developmental work on ZPR-VI, ZPR-IX, and Juggernaut is summarized, followed by a summary of EBR-I operation and development of… more
Date: February 15, 1961
Partner: UNT Libraries Government Documents Department
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Reactor Development Program, Progress Report, May 1961

Description: General research and development on water-cooled and sodium-cooled reactors are reported along with specific developments on EBWR, BORAK-V, EBR-I, and EBR-H. Thermal and fast reactor safety studies are summarized in terms of fuel-coolant chemical reactions, kinetics of oxidation and ignition of reactor materials, core meltdown studies, and a sodium vapor pressure furnace. Evaluations were made of improved fast reactors for central station power and of a 50-Mwe Prototype Organic Power Reactor (P… more
Date: June 15, 1961
Partner: UNT Libraries Government Documents Department
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