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Steam Generators for High-Temperature Gas-Cooled Reactors
Report describing a study that "was undertaken to provide a sound basis both for the optimization of either axial-flow or cross flow steam generators and for the evaluation of the relative merits of major design features" (p. 2).
Computer Programs Using Zonal Harmonics for Magnetic Properties of Current Systems with Special Reference to the IBM 7090
Report that "discusses the magnetic vector and scalar potentials, magnetic field components and their derivatives, and flux linkage for single current systems, and the mutual inductance, forces and torques between two such systems, whose axes are coplanar but not necessarily coincident" (p. 1).
Thermodynamic Calculations Relating to Chloride Volatility Processing of Nuclear Fuels: [Part] 2. The Capacity of Chlorine for Transporting Plutonium Tetrachloride Vapor During Reaction of U3O8-PuO2 with Carbon Tetrachloride
Report issued by the Oak Ridge National Laboratory discussing thermodynamic calculations of nuclear fuels. As stated in the introduction, "the equations developed in this report could be used to calculate the capacity of chlorine for transporting plutonium tetrachloride" (p. 2). This report includes tables, and illustrations.
Review of Radioisotopes Program, 1964
Report issued by the Oak Ridge National Laboratory discussing a review of the Radioisotopes Program during 1964. Research and experimental projects conducted during 1964 is presented. This report includes tables, illustrations, and photographs.
Numerical Computation of the Characteristic Values of a Real Symmetric Matrix
Report discussing the use of computers to determine the characteristic values of a symmetric matrix. Topics include dealing with the accumulation of round-off errors.
Laboratory Development of a Tributyl Phosphate Solvent Extraction Process for Processing 20% Enriched Uranium Alloy Fuel
Report containing a preliminary chemical flowsheet "for the preparation of feed and two solvent extraction cycles for the processing of silicon-containing aluminum-uranium alloy, 20% enriched, fuel elements" (p. 2).
An Experimental Investigation of Instantaneous-Collapse and Creep-Buckling Characteristics of Cylindrical Shells
Report tests "conducted on nominal 8.0-in.-OD by 0.25-in.-wall and 4.0-in.-OD by 0.12-in.-wall specimens made from commercial pipe and tubing" (p. 1).
Health and Safety Laboratory Environmental Quarterly Report: October 1, 1977, Appendix
Report that presents information regarding chemical and radioactive pollution in the world. This appendix includes a quarterly report of the deposition of strontium-90 and measurements of radionuclides and lead in surface air, milk, and tapwater. Includes a table of radionuclides.
Engineering Development of a Foam Column for Countercurrent Surface-Liquid Extraction of Surface-Active Solutes
Report documenting the problems, design, and operation of countercurrent liquid-foam columns.
Health and Safety Laboratory Environmental Quarterly Report: June 1, 1977 - September 1, 1977
Report that presents information regarding chemical and radioactive pollution in the world. Includes tabulations of radionuclides and lead in milk, food, and tapwater.
Fuel Cycle Costs for a Plutonium Recycle System
Report containing the estimated costs of the chemical and metallurgical steps in plutonium recycling for large desalination reactors.
Type 316 Stainless Steel, Inconel, and Haynes Alloy No. 25 Natural-Circulation Boiling-Potassium Corrosion Test Loops
Report issued by the Oak Ridge National Laboratory discussing natural-circulation corrosion test loops. As stated in the abstract, "an investigation was undertaken to determine the compatibility of conventional nickel, iron, and cobalt-base high-temperature alloys with boiling potassium. The tests were designed to obtain quantitative information on the dissolution of the container alloys by condensing potassium and the subsequent deposition of solute in the subcooled liquid region of the test device" (p. 1). This report includes tables, illustrations, and illustrations.
Microscopic and Autoradiographic Studies of Distribution of Uranium in the Rat Kidney
Report issued by the Oak Ridge National Laboratory discussing studies conducted on uranium retention in rat kidneys. Methods, equipment, and results of the studies are presented. This report includes tables, illustrations, and photographs.
Corn Pone: A Multigroup, Multiregion Reactor Code
Report covering the development of a set of difference equations for machine solution. In addition, this report serves as user's manual for Corn Pone, which is a code for the Oracle, the Oak Ridge National Laboratory computer.
Evaluation of an Engineering Demonstration of the Modified Zirflex and Neuflex Processes for the Preparation of Solvent Extraction Feeds from Unirradiated Zirconium-Base Reactor Fuels
Report that investigates the concept of using ammonium fluoride-oxidant systems to dissolve spent U-Zr-Sn reactor fuels in both batch and continuous operation.
Development of the Assembly Method for Fuel Elements for the Advanced Test Reactor
Report regarding the development of fuel elements for the Advanced Test Reactor. The designs for the side plates and joints are documented, as well as the assembly process of the fuel element.
Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor
Report containing the description and design of U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor. Topics include the requirements of core materials, materials specifications, manufacturing procedures, and shipping preparation.
Electronic Instrumentation for a Multiple-Crystal Gamma-Ray Scintillation Spectrometer
Report that contains descriptions of the electronic equipment used with the multiple-crystal gamma-ray spectrometer.
Health Physics Research Reactor Hazards Summary
Report describing the design and operation of the Health Physics Research Reactor, its core, and its support structures.
Molten-Salt Reactor Program Quarterly Progress Report: October 1957
Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Molten-Salt Reactor Program. Descriptions of the progress and studies conducted is presented. This report includes tables, illustrations, and photographs.
Mechanical Properties of Some Refractory Metals and their Alloys
Report regarding the mechanical properties of Niobium, Molybdenum, Tantalum, and Tungsten alloys. Includes a review of the scant literature regarding these elements.
Maritime Reactor Project Annual Progress Report for Period Ending November 30, 1963
Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Maritime Reactor Program. Progress and studies conducted during 1963 are presented. This report includes tables, illustrations, and photographs.
Applied Health Physics Annual Report for 1963
Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs.
Status Report Number Three on Clinch River Study
Report describing the progress made in the Clinch River Study for the period May to October 1961. This report is based off of multiple reports of water sampling conducted across six stations in order to evaluate the safety and radioactive content of the Clinch River.
High-Density Concrete for Gamma and Neutron Attenuation
Report issued by the Oak Ridge National Laboratory discussing the development of a high-density concrete. As stated in the abstract, "the basic approach to high-density concrete mix design is reviewed to show that theoretical calculations for concrete mixes do give results that are reliable" (p. 1). This report includes tables, illustrations, and photographs.
Analytical Chemistry Division Annual Progress Report, December 31, 1960
Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.
Analytical Chemistry Division Annual Progress Report, May 20, 1970
Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.
Army Reactors Program Annual Progress Report: 1962
Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
Gas-Cooled Reactor Project Quarterly Progress Report: September 1960
Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Gas-Cooled Reactor Project Quarterly Progress Report: December 1960
Report documenting the research and development of the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Gas-Cooled Reactor Project Quarterly Progress Report: March 1961
Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Gas-Cooled Reactor Project Quarterly Progress Report: June 1961
Report documenting the ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Gas-Cooled Reactor Project Quarterly Progress Report: September 1961
Report containing the ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Gas-Cooled Reactor Project Quarterly Progress Report: December 1961
Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Gas-Cooled Reactor Project Quarterly Progress Report: March 1962
Report documenting the ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962
Report documenting research and developments made by the Maritime Reactor Program of the Oak Ridge National Laboratory.
Maritime Reactor Project Annual Progress Report, November 30, 1961
Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Maritime Reactor Program. Progress and studies conducted during 1961 are presented. This report includes tables, illustrations, and photographs.
Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Molten-Salt Reactor Program Quarterly Progress Report: October 1958
Report documenting ongoing experiments, designs, and tests undertaken by the Oak Ridge National Laboratory for the Molten-Salt Reactor Project.
Molten-Salt Reactor Program Quarterly Progress Report: April 1959
Report documenting ongoing experiments, designs, and tests undertaken by the Oak Ridge National Laboratory for the Molten-Salt Reactor Project.
Molten-Salt Reactor Program Quarterly Progress Report: July 1960
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1962
Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Descriptions of design, construction, and experimental progress are presented. This report includes tables, illustrations, and photographs.
Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1971
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending August 31, 1968
From introduction: "Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program."
Nuclear Safety Program Semiannual Progress Report: for Period Ending June 30, 1962
Report that describes the research and developments of the Nuclear Safety Research and Development Program of the Oak Ridge National Laboratory.
Oak Ridge Analytical Chemistry Division Annual Progress Report: 1961
Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.
Reactor Chemistry Division Annual Progress Report for Period Ending January 31, 1962
Report containing the ongoing research and developments of the Oak Ridge National Laboratory's Reactor Chemistry Division.
Thermonuclear Division Semiannual Progress Report, January 31, 1961
Report describing ongoing progress made at the Oak Ridge National Laboratory's Thermonuclear Division.
Thermonuclear Project Semiannual Report For Period Ending October 31, 1962
Report describing progress made on the Oak Ridge National Laboratory Thermonuclear Program.
Thermonuclear Project Semiannual Report, January 31, 1959
Report describing progress made on the Oak Ridge National Laboratory Thermonuclear Program called the "Sherwood Project."