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- Hazard Summary Report Experimental Breeder Reactor II (EBR-II)
- From Forward: "This report describes the present conceptions of the Experimental Breeder Reactor-II as well as the safety procedures and precautions which are currently anticipated for its operation."
- Frequency Response Measurements of the EBWR Automatic Steam by-Pass Valve Control System
- Report describing the steam by-pass system of the Economic Simplified Boiling Water (EBWR) Reactor. The control system and errors are described.
- Hazard Summary Report on the Argonne Low Power Reactor (ALPR)
- Report regarding a nuclear reactor designed to operate in arctic conditions. This report includes a design of such a reactor and potential hazards.
- Preliminary Design Requirements Argonne Boiling Reactor (ARBOR) Facility
- From Introduction: "Descriptions of the functional requirements of the facility, together with preliminary concepts of methods for meeting them, are presented in this prospectus."
- Design and Performance Characteristics of Magnetic Jack-Type Control Rod Drive
- Report concerning the design of the magnetic jack, which is a "hermetically sealed, step-motion linear motor which satisfies the need for a reliable, low-cost, nuclear reactor control rod drive." (p. 5)
- Hazards Evaluation Report Associated with the Operation of EBWR at 100 MW
- Hazard report on the Experimental Boiling Water Reactor that covers the basic modifications to the plant as designed to increase the present operating design rating of 20 Mw(t) to a new rating of 100 Mw(t). Changes and additions to the plant, core, reactor vessel, and other major components are shown. An analysis of the effects of the changes on the performance and safety of the reactor is presented.
- Hazard Summary Report on the Experimental Boiling Water Reactor (EBWR)
- Report discussing possible hazards and preliminary safeguards for a 20-megawatt Experimental Boiling Water Reactor (EBWR) power plant
- Terminal Report on the Mighty Mouse High-Flux Research Reactor Project
- From Introduction: "More specifically, it describes the basic reactor complex, the problems involved, the various approaches pursued, the present status and estimated cost of the project, along with recommendations for future research and development essential to the successful culmination of the project."
- Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements
- Report issued by the Argonne National Laboratory over studies conducted on the Argonne Low Power Reactor. As stated in the abstract, "this report describes the manufacture of 1150 fuel core blanks, of which 816 were used in the fabrication of fuel elements. Development, casting, hot and cold rolling, cleaning, and punching of core blanks are discussed, as are nondestructive testing and evaluation of the manufacturing processes" (p. 7). This report includes tables, illustrations, and photographs.
- Hazards Summary Report on the Oxide Critical Experiments
- Report describing a zero-power reactor facility (ZPR-VII), its systems, and associated hazards.
- Advanced Designs of Magnetic Jack-Type Control Rod Drive
- Report containing information regarding magnetic jacks, which are devices used "for positioning the control rods in a nuclear reactor, especially in a reactor containing water under pressure" (page 9). Contains a description of the device, its use, test results, and illustrations.
- Initial Testing and Operation of the Argonne Low Power Reactor (ALPR)
- From Introduction: "In this report data are presented on the various phases of the program, together with test results and recommendations for future plant improvements. The ALPR prototype has proven to be a stable and reliable nuclear power plant."
- Summary Report on the Hazards of the Argonaut Reactor
- From Summary: "This report covers installation of Argonaut Reactor at the Du-Page site of the Argonne National Laboratory."
- The Fabrication of Certain Jacketed Uranium Helices
- Report describing the fabrication of Doppler Helices, which were 1/8 inch diameter x 12 foot long uranium core completely enclosed within a thin metal jacket and wound into a spring or helix shape.
- Manufacture of Fuel Plates for the Experimental Boiling Water Reactor
- From Abstract: "Discussed in the paper are the production of the uranium fuel alloy, the fabrication of the cladding components from Zircaloy-2 ingot, the assembly, welding, evacuation, and sealing of the cladding billets, the jacketing of the cladding billets with steel, and the roll bonding, heat treatment, stripping, and cleaning of the fuel plates. Evaluation of the fuel plates produced is also included."
- A Shielded Metallograph for Remote Metallography
- From Introduction: "This report presents the specific design requirements arising from these initial decisions, followed by description and keyed illustrations of the various features of the installation. The Bausch and Lomb Research Metallograph was the instrument chosen as being most readily adapted to the over-all plan."
- Spectroscopy of Uranyl Salts in the Solid State
- From Introduction: "The interpretation of the fluorescence and absorption spectrum of the uranyl ion, indicated in this introduction, is based on the spectroscopic work of Nichols, Howes and co-workers (1914-1919), Dieke and van Heel (1925), Moerman and Kraak (1939), and Freymann and co-workers (1946-1948); on infrared studies (cf., Section 3 below) and Raman spectra; but most of all, on the work of Dieke, Duncan, and co-workers, carried out in 1943-1944 under the Manhattan District program. In the present chapter we will review briefly the earlier investigations in the field of uranyl salt and spectroscopy and give a somewhat more detailed summary of the results of Nichols and Howes and, particularly, of Dieke and co-workers."
- Five-year climatological summary, July 1949-June 1954, Argonne National Laboratory, DuPage County, Illinois
- Report documenting various meteorological measurements for the purpose of understanding the possible dispersion of radioactive material.
- Roll Cladding Uranium-Zirconium and Uranium-Zirconium-Niobium Alloys with Zircaloy-2 for Plate-Type Fuel Elements
- From Abstract: "Investigations were made of alternate methods of bonding fuel shapes and the use of alternate core alloys in flat plates. Alternations and additions were made to development facilities needed to fabricate roll-clad plates for the EBWR core. Pilot production of EWBR-type plates proved that the plate cladding process could be adapted to production facilities."
- Resistance of Materials to Attack by Liquid Metals
- From Forward: "As their contribution, the Metallurgy Division of Argonne National Laboratory was asked to assemble all available unclassified and declassifiable data on the resistance of materials to attack by liquid metals. The resulting collation of data is contained in this report."
- Neutron Scattering Angular Distribution
- From Introduction: "The remainder of this report describes the experiment and analytical methods which were used to obtain corrected cross sections in the representation shown in the graphs."
- A General Method for Comparing Thermal Performance of Fuel Element Geometries and Coolants for Non-Boiling Reactors
- Report containing a method "for comparing the influence of various fuel element geometries on rector core shape or different specifications of thermal performance"(p. 7).
- Calculations on U235 Fission Product Decay Chains
- Report of equations for calculating decay of U235. The introduction states" Calculations have been made on the U235 fission product decay schemes. The results for a typical example, that of a reactor operating at 1000 kilowatts for 180 days, have been tabulated and graphed. General formulae have been used so that the results can be applied for any power level and any time of irradiation" (p. 2).
- IsotopesProduction Reactor: Summary of Complete Design
- Report describing an Isotope Production Reactor, which may be of interest to industrial groups studying the possibilities of entering the radioactive isotopes production field. Detailed drawings and specifications for the construction of the reactor are included.
- Argonne National Laboratory Annual Report: 1957
- Report issued by the Argonne National Laboratory discussing the variety of work done at the laboratory during the year of 1957. This report includes tables, illustrations, and photographs.
- Argonne National Laboratory Annual Report: 1958
- Report issued by the Argonne National Laboratory discussing the variety of work done at the laboratory during the year of 1958. This report includes tables, illustrations, and photographs.
- Engineering, Construction and Cost of the Argonaut Reactor
- Report describing the Argonaut Reactor located at the Argonne National Laboratory. Photographs and descriptive drawings of the reactor are included.
- The Process Equipment and Protective Enclosures Designed for the Fuel Fabrication Facility: Facility #350
- Report issued by the Argonne National Laboratory discussing the design and construction of equipment for reactor fuels. As stated in the summary, "the report describes the development, prototype construction, methods of testing, and leak detection of a modular hood design to be used in housing equipment and processes for the Argonne National Laboratory Fuel Fabrication Facility" (p. 9). This report includes tables, illustrations, and photographs.
- The EBWR: Experimental Boiling Water Reactor
- Report issued by the Argonne National Laboratory discussing the Experimental Boiling Water Reactor (EBWR) power plant. Designs of the final EBWR power plant are presented. This report includes tables, illustrations, and photographs.
- Argonne National Laboratory Annual Report: 1956
- Report issued by the Argonne National Laboratory discussing the variety of work done at the laboratory during the year of 1956. This report includes tables, illustrations, and photographs.
- Two-Phase Air-Water Flow Phenomena
- Report issued by the Argonne National Laboratory discussing two-phase flow studies that were conducted "to obtain empirical density relationships and pressure drop friction factors for two-phase mixtures" (p. 11). This report includes tables, illustrations, and photographs.
- Lecture Notes on Reactor Shielding
- Report issued by the Argonne National Laboratory discussing the shielding of radiation produced by nuclear reactors. As stated in the introduction, "these lectures will be an attempt to discuss the design of a reactor shield and the solution of the associated shielding problems by simple hand-computing methods" (p. 19). This report includes tables, and illustrations.
- Summary of Meteorological Data Taken at Argonne National Laboratory, Du Page County, Illinois, July 1952 Through June 1953
- Report issued by the Argonne National Laboratory discussing meteorological data collected between 1952 and 1953. Wind, temperature, pressure, and precipitation studies are presented. This report includes tables, illustrations, and a map.
- Quarterly Progress Report on Reactor Development: 4000 program
- Report issued by the Argonne National Laboratory discussing progress made on reactor development. Progress made on the core, pressure vessel and shield, and the power plant are presented. This report includes tables, and illustrations.
- The Transient Behavior of Single-Phase Natural Circulation Water Loop Systems
- Report issued by the Argonne National Laboratory discussing single-phase water loop systems. As stated in the introduction, "the principal objective of this study was to determine the reliability of the calculations based upon numerical solutions of finite-difference energy and flow equations" (p. 9). This report includes tables, illustrations, and photographs.
- Selected Values of the Physical Properties of Various Materials
- Report issued by the Argonne National Laboratory discussing selected physical properties of various solids, liquids, and gases of interest in nuclear reactor heat transfer and fluid flow analysis. In most cases, values for thermal conductivity specific heat, density, viscosity, and Prandtl numbers are given as functions of temperature. This report includes tables, and illustrations.
- Argonne High-Flux Research Reactor: AHFR Conceptual Design Study
- Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.
- Summary of Conference on the Toxicity of Carbon 14 Held at Argonne National Laboratory, January 15-16, 1952
- Report issued by the Argonne National Laboratory discussing the Conference on the Toxicity of Carbon 14. At the outset of the meeting it was emphasized that the group was brought together to discuss work which had a bearing on the toxicity of C14 compounds used either clinically or industrially, and the hope was expressed that the group might be able to reach some conclusions on these matters. This report includes tables.
- Heat Generation in Irradiated Uranium
- Report issued by the Argonne National Laboratory discussing the heat generation of irradiated uranium. Methods of heat production in uranium are presented. This report includes tables, and illustrations.
- Electronic Distribution Functions and Thermodynamic Properties at High Temperatures
- Report issued by the Argonne National Laboratory discussing the thermodynamics and electronic distribution of high temperatures. As stated in the introduction, "in the present paper, a model for computing is described which takes into account in detail the interactions between bound electrons and the average interaction of the bound electrons with the free ones" (p. 4). This report includes tables, and illustrations.
- Engineering Properties of Diphenyl
- Report issued by the Argonne National Laboratory discussing engineering properties of diphenyl. As stated in the abstract, "data collected from the literature on the vapor pressure, enthalpy, liquid density, and vapor density of pure diphenyl are presented. A Mollier diagram, a temperature entropy diagram, and data on viscosity of diphenyl as a function of temperature are also presented" (p. 5). This report includes tables, and illustrations.
- A Physical Determination of the Conversion Ratio of the Experimental Breeder Reactor
- Report issued by the Argonne National Laboratory discussing the Experimental Breeder Reactor (EBR). Descriptions and methods of the EBR are presented. This report includes tables, and illustrations.
- Progress Report on the Argonne-Oak Ridge Digital Computer
- Report issued by the Argonne National Laboratory discussing a progress report on the Argonne-Oak Ridge digital computer. This report is an interim report, whose primary value is that it has forced those engaged in the work to give concrete expression to what they have been doing and thinking about up to this point. This report includes tables, illustrations, and photographs.
- Reactor Engineering Division Quarterly Report: December 1, 1953 Through March 30, 1954
- 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.
- Particle Accelerator Division Summary Report: April 15, 1958 through October, 1958
- Report issued by the Argonne National Laboratory discussing a summary report of work completed between April and October, 1958. Summaries of the studies conducted and work completed are presented. This report includes tables, and illustrations.
- The Relative Thermal Conductivities of Liquid Lithium, Sodium, and Eutectic NaK, and the Specific Heat of Liquid Lithium
- Report discussing the relative thermal conductivities of liquid lithium, sodium, and eutectic NaK, and the specific heat of liquid lithium, as well as the methods and materials used to determine this information.
- Reactor Engineering Division Semiannual Report December 1, 1951 through May 31, 1952
- This report describes the construction of a reactor and the research conducted in the reactor such as solid fuel and liquid fuel research, boiling reactor experiments, CP-6 bond testing program, and water quality control experiments for CP-6 program.
- The Manufacture Of Enriched Uranium Fuel Slugs for the Experimental Breeder Reactor
- This report describes the specifications, materials and the sequence of operations used to found and fabricate the first charge of enriched uranium fuel in the Experimental Breeder Reactor.
- Chemistry Division, Section C-1, Summary Report For October, November and December 1951
- Report describing the research and development activities related to nuclear chemistry and radiochemistry and basic chemistry conducted by the Argonne National Laboratory Chemistry Division, Section C-1.
- Aqueous Corrosion of Uranium and Alloys: Survey of Project Literature
- This report describes corrosion rate of uranium in hydrogen-saturated water appears to be constant with respect to time after a brief induction period and to involve only one type of over-all reaction, in which pitting effects are slight or nonexistent.