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Molten-Salt Reactor Program Semiannual Progress Report, January 31, 1964
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Solid State Division Annual Progress Report, May 31, 1964
Report containing ongoing research and development of the Solid State Division of the Oak Ridge National Laboratory.
Spectra of Gamma Rays Produced by the INteraction of ~160-MeV Protons with Be, C, O, Al, Co, and Bi
Report concerning the production of gamma ray spectra of gamma rays by the interaction of ~160-MeV protons with beryllium, carbon, oxygen, Aluminum, carbon monoxide, and bismuth. This also includes descriptions of the apparatus used and a discussion of the results.
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.
Thorium-Uranium-233 Oxide (Kilorod) Facility : Rod Fabrication Process and Equipment
Report documenting "the design, construction, and operation of the Kilorod Facility and its fabrication equipment" (p. 42) as well as its economic viability.
Oak Ridge Analytical Chemistry Division Annual Progress Report: 1963
Report containing the ongoing research and development of the Oak Ridge National laboratory's Analytical Chemistry Division.
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.
A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables
Report presenting the calculation of the costs incurred in shipping irradiated uranium-containing fuel elements. A computer code that designs a cask and calculates the shipping costs is presented. By use of the code, shipping costs were calculated for typical reactor fuels.
Gas-Cooled Fast Reactor Concepts: a Study
Report describing the performance characteristics of gas-cooled fast reactors, which compare well with those of sodium-cooled fast reactors. With oxide fuel and helium, CO2, and SO2 coolant at pressures of 1000 to 1500 psia, the reactors have slightly higher breeding ratios than comparable sodium-cooled reactors.
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.
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969
Report documenting the ongoing research and development of the Oak Ridge National Laboratory's Chemical Technology Division.
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: 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: June 1961
Report documenting the ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Chemical Technology Division Annual Progress Report, August 31, 1960
Report documenting the ongoing research of the Oak Ridge National Laboratory's Chemical Technology Division. This report includes tables, diagrams, graphs, and articles related to chemical technology.
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.
Oak Ridge Analytical Chemistry Division Annual Progress Report: 1962
Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Analytical Chemistry Division. Instrumentation, analytical methods, reactor projects, service analysis, and special research is presented. This report includes tables, illustrations, and photographs.
Army Reactors Program Annual Progress Report: 1962
Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
Oak Ridge Analytical Chemistry Division Annual Progress Report: 1962
Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Chemistry Division.
Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962
Report issued by Oak Ridge National Laboratory that discusses progress and work performed by the Chemical Technology Division.
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1963
Report issued by Oak Ridge National Laboratory that describes research and progress at the Chemical Technology Division.
Gas-Cooled Reactor Project Semiannual Progress Report: September 1962
Report documenting the design and testing progress of 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.
Oak Ridge Metals and Ceramics Division Annual Progress Report: 1962
Report documenting research and developments made by the Metals and Ceramic Division of the Oak Ridge National Laboratory.
Oak Ridge Metals and Ceramics Division Annual Progress Report: 1963
Report documenting research and developments made by the Metals and Ceramic Division of the Oak Ridge National Laboratory.
Molten-Salt Reactor Program Semiannual Progress Report: for Period Ending August 31, 1962
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 January 31, 1963
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.
Instrumentation and Controls Division Annual Progress Report: for Period Ending September 1, 1962
Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
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).
Low-Radioactivity-Level Waste Treatment. Part II: Pilot Plant Demonstration of the Removal of Activity from Low-Level Process Wastes by a Scavenging-Precipitation Ion-Exchange Process
Report documenting the process of decontaminating low-activity fuel waste water via the Scavenging-Precipitation Ion-Exchange process. This includes analyses of the costs of the process as well as a description of the operation of the pilot plant.
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.
Evaluation of a Reduced Pressure Backflow Preventer Using Activation Analysis
Report containing tests performed to evaluate a reduced pressure backflow preventer. This includes preliminary tests, resulting improvements, and final rests. Appendices begin on page 23.
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.
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.
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.
Civil Defense Research Project Annual Progress Report: March 1966 - March 1967
Report containing the results of Oak Ridge National Laboratory's research relating to civil defense.
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 Fabrication Procedures for Core B Fuel Elements for the Enrico Fermi Fast Breeder Reactor
Report describing the "development procedures for fabricating the proposed Core B fuel element of the Enrico Fermi Fast Breeder Reactor" (p. 1). This includes a description of various components, reactor assembly, and reported conclusions. Appendices begin on page 57.
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.
The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings
Report containing a series of drawings detailing the Oak Ridge National Laboratory's high flux isotope reactor, its surroundings, and its systems.
Health Physics Division Annual Progress Report, January 31, 1955
Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Instrumentation and Controls Division Semiannual Progress Report, January 31, 1955
Report containing the ongoing progress and developments of the Instrumentation and Controls Division of Oak Ridge National Laboratory.
Nuclear Safety Program Annual Progress Report: for Period Ending December 31, 1968
Report containing material from several Oak Ridge National Laboratory groups regarding nuclear safety.
Solid State Division Semiannual Progress Report, February 29, 1956
Report documenting the ongoing research and developments of the Solid State Division of the Oak Ridge National Laboratory. Contains related papers and other publications.
Tables of the Racah Coefficients
Report containing tables of the Racah Coefficients.
The HRE Simulator: An Analog Computer for Solving the Kinetic Equations of a Homogeneous Reactor
Report documenting the computer-assisted evaluation of kinetic equations that express reactor power and temperature as functions of time.
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.
The Biocoenetic Process in an Estuarine Phytoplankton Community
Report discussing "[a]n ecological theory of adaptation at the community level of organization" focused around an estuary and its resident life forms.
A Revision of Computer Code POWERCO (Cost of Electricity Produced by Nuclear Power Stations) to Include Breakdowns of Power Cost and Fixed Charge Rates
Report that "describes a new version of the code, POWERC-50, which contains several changes" to the previous code, POWERCO-25, which was used to calculate "the levelized cost of electricity produced by nuclear power stations" (p. 1)