Technical Report Archive & Image Library (TRAIL) - 339 Matching Results
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- A 37,500 KW Power Reactor with Competitive Possibilities
- The following report follows the study on economics of nuclear power generation using a light water reactor.
- 6144-Channel Time-of-Flight Analyzer
- Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
- Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core
- From abstract: "explain all important features pertaining to a new pulsed irradiation reactor, the Capsule Driver, Core, and to analyze the potential problems and hazards of operating this reactor in the existing Spert IV facility."
- Advanced Test Reactor Burnout Heat Transfer Tests
- From abstract: "Results of burnout test to determine the limiting heat flux in a simulated Advanced Test Reactor fuel element channel."
- Advanced Test Reactor: Final Shielding Design Report
- From abstract: "This report has been prepared as a design reference document describing the calculation methods and engineering results for shielding analysis work done during the design of the Advanced Test Reactor."
- Advanced Test Reactor Servo Regulator Rod Test Program
- From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."
- Advanced Test Reactor Turbo Report
- From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."
- 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.
- An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel
- Report that "describes a nondestructive tester and some of its applications in measuring 10 to 100 µg of uranium surface contamination on unirradiated, low enrichment, uranium fuel elements" (p. ii).
- Analog Computer Simulation of a Pulsed Extraction Column
- Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).
- Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model
- Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
- 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 for Period Ending November 15, 1964
- 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.
- The Application of Data Processing Techniques to a Maintenance Work Control Program
- Description of a data collection and reporting system which was devised and installed in the Union Carbide Nuclear Company's Y-12 Plant Maintenance 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.
- Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956
- Report issued by the Oak Ridge National Laboratory discussing work completed by the Applied Nuclear Physics Division during 1956. Summaries of experiments conducted and project developments are presented. This report includes tables, illustrations, and photographs.
- Argonne High-Flux Research Reactor: AHFR Conceptual Design Study
- Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.
- Argonne National Laboratory Metallurgy Division Annual Report: 1963
- Annual report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963 including progress related to experiments, programs, and studies. 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, 1961
- Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations.
- 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.
- Gas-Cooled Reactor Project Semiannual Progress Report: March 1964
- Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. From summary: "A study was made of the effect of the energy of extraneous source neutrons on the amplitudes of higher modes in the flux distribution of a subcritical reactor."
- Army Reactors Program Annual Progress Report: 1962
- Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
- Automatic Mass Spectrometer for Isotopic Analysis of Lithium
- Report discussing an improvement program on lithium mass spectrometers.
- An Automatic Monitor for As76 Concentrations in Reactor Cooling Water
- Report that describes the development, design, and operation of a prototype instrument meant to monitor the As76 concentration in reactor cooling water streams.
- Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements
- Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.
- Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C
- Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations.
- Chemical Coolants for Machining Uranium in the Presence of Trace Amounts of Chloride
- Discussion of laboratory tests to reduce uranium corrosion.
- Chemical Processing Instrumentation and Control Research Program
- Report regarding the chemical processing instrumentation designs and problems at the Idaho Chemical Processing Plant.
- 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, 1961
- Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.
- The Cold Pressing of Sinterable UOâ‚‚
- The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.
- 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.
- A Computer Program for Determining First-Collision Neutron Doses
- Data processing program written to compute the neutron dose received by individuals exposed in a nuclear excursion.
- 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).
- Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation
- Report issued by the Argonne National Laboratory discussing condensation theories of metal vapors. As stated in the introduction, "the objectives of this research then are critical analysis of condensation theories and data for metal vapors and experimental evaluation of the resistance to condensation for a representative metal such as mercury" (p. 18). This report includes tables, illustrations, and photographs.
- 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.
- Corrosion Studies in Simulated N-Reactor Secondary System Water Environment
- Report containing the procedures and results of tests made to determine the corrosion resistance of materials in a simulation of Hanford Laboratories' N-Reactor secondary system water environment.
- Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant
- Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.