Technical Report Archive & Image Library (TRAIL) - 144 Matching Results
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- 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.
- 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.
- Analytical Chemistry Division Annual Progress Report, September 30, 1968
- Report containing the ongoing research and development of the Oak Ridge National laboratory's Analytical Chemistry Division.
- 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.
- 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.
- Army Reactors Program Annual Progress Report: 1962
- Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
- Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor
- Report that describes the Oak Ridge National Laboratory Experimental Gas-Cooled Reactor, problems with the procurement and assembly of its components, and its economic feasibility.
- 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.
- 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).
- 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.
- 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.
- 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.
- Chemical Technology Division Annual Progress Report, May 31, 1968
- 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.
- 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)
- 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.
- 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).
- 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.
- 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.
- 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.
- 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.
- 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.
- 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.
- Electronuclear Research Division Annual Progress Report, December 31, 1963
- Report containing ongoing research and development taking place at the Oak Ridge National Laboratory's Electronuclear Division.
- 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.
- 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.
- 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.
- 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.
- 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.
- 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).
- 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.
- Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968
- From Foreword: "Report containing information about ongoing research and development taking place in the Oak Ridge National Laboratory's Fuels and Materials Development Program. This includes a series of test reports covering such subjects as reactor fuels, the development of nitride fuels, and the effects of radiation on structural materials."
- Gas-Cooled Fast Reactor Concepts
- 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: 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.