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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.
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.
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.
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.11
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 2.13
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 2.14
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.
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.
Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959
Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1959
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1963
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1964
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1964
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
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.
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.
Tables of the Racah Coefficients
Report containing tables of the Racah Coefficients.
The High Flux Isotope Reactor: Volume 1, A Functional Description
Report containing a description of the Oak Ridge National Laboratory's High-Flux Isotope Reactor (HFIR) and its operation.
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.
The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah
Report containing a survey of the radiation from the nuclear ship Savannah in order to determine the dose rate for people aboard.
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.
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.
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.
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.
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.
In-Pile Test of Prototype ML-1 Fuel Elements
Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.
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.
An Investigation of the Instantaneous and Creep Buckling of Initially Out-of-Round Tubes Subjected to External Pressure
Report regarding a method for predicting the instantaneous and creep buckling characteristics of tubes to lateral external pressures using a small sample of 8.0-in.-o.d. stainless steel tubes. The report includes the development and application of buckling theories. Appendix begins on page 71.
Environmental Analysis of NS "Savannah" Operation at Camden
Report regarding the nuclear ship "Savannah" and the consequences of nuclear activity that it would release into the surrounding area at its proposed startup site, Camden, New Jersey. Scenarios include activity being released into the atmosphere and hydrosphere, damage to equipment, and effects on a population.
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.
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.
Design Report for Nuclear Merchant Ship Reactor Pressurized Water Loop at Oak Ridge National Laboratory Research Reactor
Report describing a pressurized water loop that was constructed for use in the Maritime Reactor Program. The report also includes the operational experience of using the device. Appendices begin on page 48.
Superposition of Forced and Diffusive Flow in a Large-Pore Graphite
Report describing an "investigation of steady-state counter-flow of gases in a large pore graphite" by exposing it to streams of helium and argon.
Pulse Amplifier Manual
Manual for the use and repair of repair pulse amplifiers. This covers general testing routines, specific tests, and a bibliography of related materials.
Preliminary Solution Critical Experiments for the High-Flux Isotope Reactor
Report containing experiments conducted at the Oak Ridge National Laboratory's Critical Experiments Facility. These experiments involved "determining the critical parameters of the assembly with varying amounts of neutron absorber in the D20 reflector, measuring the relative neutron flux distribution for various conditions of reflector poison and fissile solution concentration, determining the ratio of the absolute thermal-neutron flux in the center of the assembly to the power in the fissile solution , and determining the effect on reactivity of reducing the hydrogen density in the central region of the assembly" (p. 1).
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.
A Comparison of Gas-Turbine and Steam-Turbine Power Plants for Use with All-Ceramic Gas-Cooled Reactors
Report that "compares gas turbines with steam turbines as means of producing electric power from gas-cooled reactors with all-ceramic fuel elements." (p. 1)
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).
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