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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
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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 engineering, separation processes and advanced reactor concepts. (J.R.D.)
Date: April 1, 1961
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Reactor Development Program Progress Report, April 1963

Description: Progress made in the reactor development program at Argonne National Laboratory is reported. Information and data are presented on Borax-V, SL-1, ZPR- III, ZPR-VI, ZPR-VII, ZPR-IX, EBR-I, EBR-II, FARET, EBWR, Treat, nology is presented along with nuclear safety. Reactor fuel element and material development is emphasized. (N.W.R.)
Date: May 15, 1963
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Reactor Development Program. Progress Report, December 1963

Description: Development progress is reported on fast reactors, liquid metal cooled reactors, ZPR-III No. 22 and 44, Z PR-VI No. 1, ZPR-IX, Borax-V, Faret, EBR-I, EBR-II, treat, Fermi Fast Breeder Reactor, critical assemblies, Argonne Advanced Research Reactor, EBWR, magnetohydrodynamic cells, thermionic cells, fuel cells, and boiling water reactors. Reactor technology is reported on fuel development, physics, heat and fluid engineering, materials development and properties, chemical separations, nuclear safety, and corrosion testing. (N.W.R.)
Date: January 15, 1964
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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 void distributions in two-phase systems. Fluidization and fluoride volatility separation, and chemical-metallurgical separation processes were studied. Advanced reactor concepts that were discusssd includsed. Basic Radiation Effects Beactor, Biogeonuclear Reactor, Fast Reactor Test Facility, compact high-power density fast reactors, AHFR hydraulic test loop, Packed Bed Reactor, and direct conversion. (For preceding period see ANL- 6328.) (B.O.G.)
Date: March 15, 1961
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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 EBR-II. Studies of reactor steam superheating concepts are reported from which conclusions are listed. In reactor safety studies, data were obtained on the extent of water reaction with various metal combinations for use in cores as function of energy input. In other work in-pile melt down studies were conducted. Operation and development of TREAT are described. Nuclear technological developments are summarized in sections on physics, fuel development, reactor components and materials, separations development, and advanced reactor development. (For preceding period see ANL- 6295.) (J.R.D.)
Date: February 15, 1961
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Reactor Development Program Progress Report, January 1963

Description: Research and development activities are reported on Borax V, ZPR- III, - VI, and -IX, EBR-I, EBR- II, and FARET. Reactor technology investigations are reported in reactor physics, reactor fuel development, viewing systems, heat engineering, and chemical separations. Research on advanced systems is reported on reactors and undersea nuclear power applications. Nuclear safety development in thermal and fast reactors is also reported. (J.R.D.)
Date: February 15, 1963
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Reactor Development Program Progress Report, January 1964

Description: Research and development activities are reported on Borax-V, ZPR-III No. 44, ZPR-VI No. 1, ZPR-IX, EBR-I, EBR-II, EBWR, Treat, Faret, Rapsodie Reactor, critical assemblies, fast reactors, Argonne Low Power Research Reactor, Topsy, Godiva, Argonaut Reactor, Argonne Advanced Research Reactor, Rocket Fuel Test Reactor, magnetohydrodynamic cells, and fuel cells. Reactor technology and investigations are reported in reactor physics, fuels and materials development, component development, heat engineering, and chemical separations. Nuclear safety development in thermal and fast reactors is discussed. (N.W.R.)
Date: February 15, 1964
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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 (POPR). Developments in instruments, reactcr fuels and materials, reactor components, heat engineering, separations processes, and advanced reactcrs are discussed. (M.C.G.)
Date: June 15, 1961
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REACTOR DEVELOPMENT PROGRAM. Progress Report, November 1963

Description: Development progress is reported on fast reactors, liquid metal cooled reactors, ZPR-III, ZPR-VI, ZPR-IX, Borax-V, Faret, EBR-I, EBR-II, Treat, Fermi Fast Breeder Reactor, critical assemblies, Argonne Fast Source Reactor, EBWR, Argonne Advanced Research Reactor, magnetohydrodynamic cells, fuel cells, and boiling water reactors. Reactor technology is reported on fuel development and properties, physics, heat engineering, materials development, chemical separations, nuclear safety, and nondestructive testing. (N.W.R.)
Date: December 15, 1963
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