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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.
Molten-Salt Reactor Program Semiannual Progress Report, July 31, 1963
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Army Reactors Program Annual Progress Report: 1962
Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
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.
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: 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 January 31, 1963
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
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.
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.
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.
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).
The ORNL GCR-3, a 750-Mw(e) Gas-Cooled Clad-Fuel Reactor Power Plant : A Joint Design Study
Report documenting the design of the Oak Ridge National Laboratory Gas-Cooled Clad-Fuel Reactor Power Plant. This includes design criteria and parameters, costs, and descriptions of systems.
Neutron Physics Division Annual Progress Report, September 1, 1962
Report containing a series of reports from members of the Oak Ridge National Laboratory's Neutron Physics30 Division.
Gas-Cooled Reactor Project Semiannual Progress Report: March 1963
Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Thermonuclear Project Semiannual Report For Period Ending October 31, 1962
Report describing progress made on the Oak Ridge National Laboratory Thermonuclear Program.
Design Report for Nuclear Merchan 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.
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).
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.
In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C
In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.
In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C
Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Nuclear Superheat Quarterly Project Report: Twelfth Quarter, April-June 1962
From introduction: "This is the twelfth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Nuclear Superheat Quarterly Project Report: Fourteenth Quarter, October-December 1962
From introduction: "This is the fourteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Nuclear Superheat Quarterly Project Report: Thirteenth Quarter, July-September 1962
From introduction: "This is the thirteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Fuel Cycle Program Progress Report: Eleventh Quarter, January-March 1963
Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.
EVESR Nuclear Superheat Fuel Development Project: First Quarterly Report, May 4-August 31, 1962
Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fifth Quarterly Report, October-December 1962
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Sixth Quarterly Report, January-March 1963
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
EVESR Nuclear Superheat Fuel Development Project: Third Quarterly Report, December 1962-February 1963
Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.
A Proposal for the Mc2 Isochronous Cyclotron: A General Purpose High-Intensity 810-MeV Proton Accelerator
Abstract: "The Oak Ridge National Laboratory proposes to build an isochronous eight-sector proton cyclotron to provide an extracted beam in excess of 100 A at 810 MeV. The primary proton beam and the secondary meson and neutron beams will be used to investigate nuclear structure, and the interactions between elementary particles. Biomedical and Space-oriented research programs are also planned. Shielded research areas and an extensive beam transport and analysis system are provided. Theoretical and experimental studies have shown that the Mc2 Cyclotron is a practical concept; high extraction efficiencies can be obtained, and the residual radiation problems are manageable. The project would require less than seven years to complete, and would cost about $43,000,000."