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- 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.
- Gas-Cooled Reactor Project Semiannual Progress Report: September 1964
- Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
- Gas-Cooled Reactor Project Semiannual Progress Report: March 1965
- Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
- Instrumentation and Controls Division Annual Progress Report for the Period Ending September 1, 1966
- Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Instrumentation and Controls Division during 1966. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
- 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.
- 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.
- Molten-Salt Reactor Program Semiannual Progress Report for Period Ending July 31, 1964
- 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 is presented. This report includes tables, illustrations, and photographs.
- Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965
- Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs.
- Snap-8 Corrosion Program Quarterly Progress Report for Period Ending November 30, 1964
- Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Snap-8 Corrosion Program. Progress in design, operation, and experimental work is presented. This report includes tables, illustrations, and photographs.
- Health Physics Instrument Manual
- Report issued by the Oak Ridge National Laboratory discussing a Health Physics Instrument Manual. Descriptions, characteristics, and applications of different instruments are presented. This report includes tables, illustrations, and photographs.
- Interim Report on Corrosion by Zirconium-Base Fluorides
- Report issued by the Oak Ridge National Laboratory discussing studies conducted on corrosion by fluorides. Equipment, procedures, results, and analysis is presented. This report includes tables, illustrations, and photographs.
- Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums
- Report issued by the Oak Ridge National Laboratory discussing the evaporation of alloys in high vacuums. As stated in the introduction, "the investigation encompasses measurements of the evaporation rates, identification of the evaporating elements, and correlation of these measurements to the alloy composition for specimens in both the polished and oxidized conditions" (p. 2). This report includes tables, illustrations, and photographs.
- 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.
- 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.
- 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.
- Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor
- Report issued by the Oak Ridge National Laboratory discussing irradiation testing of fast breeder reactors. As stated in the introduction, "it is the purpose of this report to describe the irradiation studies carried out in support of the Core B fuel element development program" (p. 3). This report includes tables, illustrations, and photographs.
- Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV
- Report issued by the Oak Ridge National Laboratory discussing techniques to obtain measurements of alpha for enriched uranium. Descriptions of equipment and experiments used to obtain alpha are presented. This report includes tables, and illustrations.
- Optical Mapping of Oak Ridge Research Reactor Experiment Tubes
- Report issued by the Oak Ridge National Laboratory discussing optical mapping of experiment tubes. Descriptions of experiment equipment, and designs of the tubes are presented. This report includes tables, illustrations, and photographs.
- 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.
- 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.
- Preliminary Designs for Four Integrated Gas-Cooled Ceramic-Fueled and -Moderated Reactor Core and Steam Generator Units
- Report containing preliminary designs for four reactor core and steam generator units. The units, their difficulties, and the layout of the reactor building are described.
- 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.
- Calculation of Suspension Peptization
- Report regarding the combination the theories of flocculation, particle repulsion, and particle attraction in order to "understand the flocculation characteristics of TH02 suspensions" (p. 2).
- 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).
- 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.
- Metallurgy Division Annual Progress Report, September 1, 1959
- Report documenting ongoing research and development undertaken by the Metallurgy Division of the Oak Ridge National Laboratory.
- 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.
- Neutron Physics Division Annual Progress Report, September 1, 1958
- Report containing a series of reports from members of the Oak Ridge National Laboratory's Neutron Physics Division.
- Thermonuclear Project Semiannual Report, January 31, 1959
- Report describing progress made on the Oak Ridge National Laboratory Thermonuclear Program called the "Sherwood Project."
- 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).
- Aircraft Reactor Test Removal and Disassembly
- Report documenting the dissection of a reactor called the Aircraft Reactor Test (ART). Includes the removal of the reactor from its test cell, component removal, and plans for a for a disassembly building facility.
- 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.
- 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.
- Physics Division Annual Progress Report, January 31, 1964
- Report containing ongoing research and development of the Oak Ridge National Laboratory's Physics 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.
- Corrosion of the Volatility Pilot Plant INOR-8 Hydrofluorinator and Nickel 201 Fluorinator During Forty Fuel-Pprocessing Runs with Zirconium-Uranium Alloy
- Report documenting the corrosion of fluorinators of the Oak Ridge National Laboratory's volatility pilot plant. Includes descriptions of the fluorinators, their operating environments, and the results of their corrosion.
- Procedures for Fabricating Aluminum-Base ATR Fuel Elements
- Report concerning the relatively inexpensive fabrication of an aluminum-based fuel element for the Oak Ridge National Laboratory's 250-Mw Advanced Test Reactor.
- Oak Ridge National Laboratory Radioisotopes Procedures Manual
- Manual for the Oak Ridge National Laboratory's Isotopes Development Center. Includes procedures for the production, storage, and shipment of radioisotopes.
- Laboratory Development of Processes for Fixation of High-Level Radioactive Waste in Glassy Solids. [Part] 3, Wastes from the Purex Solvent Extraction Process
- Report concerning the fixation and disposal of toxic waste derived from the Purex solvent extraction process.
- 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.
- Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.1
- This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
- Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.2
- This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
- Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.4
- This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
- Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.5
- This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
- Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.6
- This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
- Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.7
- This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
- Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.8
- This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
- Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.9
- This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
- Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.10
- This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.