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75,000 KILOWATTS OF ELECTRICITY BY NUCLEAR FISSION AT THE HALLAM NUCLEAR POWER FACILITY

Description: For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)
Date: January 1, 1960
Creator: Gronemeyer, F.C. & Merryman, J.W.
Partner: UNT Libraries Government Documents Department
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Advanced Thermoelectric Power System. Final Report

Description: Development of a radioisotope-fueled thermoelectric power-conversion system for the SNAP program is discussed. The generator operates at somewhat less than 1% over-all efficiency, has a power output of approximately 1.45 watts, and has a specific power of 0.l42 watts per pound. The power-flattening device did not perform as expected. A second generator is also described which produces a maximum power of 1.6 watts, has a maximum efficiency of 1.20%, and has a specific power of 0.32 watts per pou… more
Date: January 1, 1960
Creator: Harvey, R. J.
Partner: UNT Libraries Government Documents Department
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AEC Group Shelter

Description: Report regarding the study of an underground group-shelter meant to protect against nuclear blasts, radiation, and fallout. The report presents a design for such a shelter, the minimum requirements that such a shelter should meet, a description of its facilities, illustrations, and an operating manual.
Date: January 1960
Creator: Holmes & Narver
Partner: UNT Libraries Government Documents Department
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An Aerodynamic Raindrop Sorter. Technical Progress Report No. 1.

Description: A pilot model of an Aerodynamic Raindrop Sorter was constructed along the lines suggested by mathematical analysis. The function of the analyzer is to sort natural rain according to drop size and to collect the sorted drops for further analysis. The pilot model, a small wind tunnel inclined at 45 deg to the horizontal, demonstrated the feasibility of aerodynamic rain drop sorting over a wide range of drop sizes. (auth)
Date: January 1960
Creator: Dingle, A. Nelson & Brock, Fred V.
Partner: UNT Libraries Government Documents Department
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Apparatus for Determining Linear Thermal Expansions of Materials in Vacuum or Controlled Atmosphere

Description: An apparatus for determining linear thermal expansion data up to 1350 deg C for materials that cannot be heated in air is described. Expansion is not measured directly, but is derived from the differential expansion between the material being tested and the materials of construction of the dilatometer. The apparatus is calibrated against published data on the linear thermal expansion of both fused silica and polycrystalline tungsten metal. It can be operated either as a high-vacuum or as a cont… more
Date: January 1, 1960
Creator: Fulkerson, S. D.
Partner: UNT Libraries Government Documents Department
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Applications for Lanthanon Oxides and Other Compounds in the Ceramic Industry

Description: Separation processes for production of pure rare earth oxides in useful quantities are discussed. A review of applications of these oxides in the ceramic industry in production of glasses, glazes, porcelain enamels, refractories, abrasives, electronic ceramics, and nuclear ceramics is also presented. 46 references.
Date: January 28, 1960
Creator: Ploetz, G. L.
Partner: UNT Libraries Government Documents Department
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Argonaut Automatic Flux Controller Design Report

Description: Report issued by the Argonne National Laboratory over design studies conducted on Argonaut reactors for training and research purposes. As stated in the abstract, "the design presented in the form of a steady-state analysis based upon the small-signal linearization of the reactor kinetics transfer function. The measured controller performance and construction details of the equipment is given" (p. 7). This report includes tables, illustrations, and photographs.
Date: January 1960
Creator: Gerba, A., Jr.
Partner: UNT Libraries Government Documents Department
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BEHAVIOR OF RUBBING MOLYBDENUM SURFACE IN SODIUM ENVIRONMENTS

Description: A study has been made of the wear and friction phenomena associated with sliding molybdenum surfaces lubricated by liquid sodium. Operating conditions included sodium temperatures from 250 to 1300 deg F, sliding speeds of from 0.22 to 2.5 nan per sec, and contact stresses of 80,000 psi. Sliding specimens consisted of a ball and a flat rectangle. Sodium was found to influence the sliding behavior of molybdenum by modifying reacted films which provided boundary lubrication. These effects were als… more
Date: January 1, 1960
Creator: Kissel, J.W.; Melton, C.W. & Glaeser, W.A.
Partner: UNT Libraries Government Documents Department
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Check-Out of Bettis Dissolved Oxygen Analyzer, Model 3

Description: A Bettis Dissolved Oxygen Analyzer was constructed, calibrated, tested on 100A-loop D, and installed at the HRT. Operating instructions for the analyzer are included in an appendix.
Date: January 14, 1960
Creator: Greeley, R. S.; Neumann, P. D.; Bolt, S. E. & Griess, J. C.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, December 1959

Description: Production of Pu nitrate from separations plants exceeded commitments. Two Np recovery runs were made, a routine one at Purex and a demonstration run at Redox. Total Np recovered in CY 1959 was 5.7 kg. The UO{sub 3} plant production and shipments also met commitments. Production of unfabricated Pu metal continued. Process studies are being conducted in Purex to resolve the problems in the Np recovery effort. A new solvent (hexone) condensate decanter was operated in Redox. Reprocessing of nonpr… more
Date: January 21, 1960
Creator: MacCready, W. K.
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program.

Description: This report presents a brief survey of the current status of technology on organic-cooled reactors.
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 1. Summary of Technical and Economic Status as of 1959

Description: The current technical and economic status for each reactor concept in the Civilian Power Reactor Program is summarized. The individual techical status reports which present detailed information will be published by AEC as TID-8518. Included in this summary are: power costs for various reactor types versus coal- fired plants; construction schedule for heavy-water natural-U reactors; and annual program costs. (T.R.H.)
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 2. Economic Potential and Development Program as of 1959

Description: The status of technology of nuclear power reactors in 1959 is reviewed. General research and engineering development activities are discussed. The reactors considered include the pressurized water, boiling water, light water moderated superheat, organic cooled, sodium graphite, gas cooled enriched fuel, gas cooled natural uranium, fast breeder, aqueous homogeneous, and heavy water. Power costs are compared with the cost of power from conventional plants. (C.H.)
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 3. Book 2. Status Report on Pressurized Water Reactors as of 1959

Description: The status of pressurized water reactors on a technical, economic, and operating experience basis is reported. Items covered include concept description, PWR objectives, general research and development prcgram, reactor data, reactor illustrations, operating experience, construction and operation schedules, and present limitations and problems. (W.D.M.)
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 3. Book 3. Status Report on Aqueous Homogeneous Reactors as of 1959

Description: The status of a program to develop a thermal breeder power reactor which is based on the Th-U/sup 233/ cycle is discussed. The general characteristics of two-region power breeder reactors which are either solution-core slurryblanket or slurry-core slurry-blanket are described. A review of studies on corrosion, physical properties, and metallurgy of fuel materials, in particular aqueous ThO/ sub 2/ suspensions, is presented. Development studies on cladding alloys are discussed. The processing of… more
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 3. Book 4. Status Report on Heavy Water Moderated Reactors as of 1959

Description: Estimates indicate that, within the D/sub 2/O-moderated natural-uranium- fuel reactor category, the lowest cost reactor will be cooled by boiling D/sub 2/ O. The margin over nonboiling is small, especially for reactors in the 100Mw(e) size and smaller. A major area in which research must be advanced before any of the reactor concepts can be successful is fuel-element fabrication and irradiation behavior. Both oxide and metallic elements have their own advantages, and each type should be develop… more
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 3. Book 6. Status Report on Sodium Graphite Reactors as of 1959

Description: The current development status of the sodium graphite reactor concept is described. The development history is summarized, and all important areas of development are discussed. The discussion of the SGR program is broken into three categories: (1) general research and development, dealing with reactor physics, fuels and materials, components, etc., (2) experimental reactors, operating or in some phase of design or constnuction, and (3) power demonstration reactors, operating or in a design or c… more
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 3. Book I. Status Report on Fast Reactors as of 1959

Description: A description of fast reactor types is given and the objectives of the AEC program on fast reactors are outlined. General research and development programs completed and in process on physics, fuel and materials, heat transfer, fluid flow, coolant chemistry, reactor safety, and components and systems are discussed. Reactors completed, under design and construction, and under study are described. (W.D.M.) A general description of ship and power plant, tabulation of principle characteristics, eco… more
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 3. Status Report on Gas-Cooled Reactors as of 1959. Book 8

Description: The technology of natural-uranium-fueled graphitemoderated gas-cooled reactor power plants is summarized for its relevance to the technology of enriched-fuel graphite-moderated systems. The technology of D/sub 2/Omoderated gas-cooled reactors is also summarized. Estimated technical performance parameters are given for the enriched-fuel prototype and for a large natural- uraniumfueled plant. Current technical status is discussed in terms of reactor physics, heat transfer and fluid flow, core mat… more
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 4. Plans for Development as of February 1960

Description: In developing the program plans presented, primary attention was given to the technological development required to achieve economically competitive nuclear power. The program objectives are given in brief and the specific reactor program is discussed in some detail. The nuclear technology program is summarized. (W.D.M.)
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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