UNT Libraries Government Documents Department - 143 Matching Results
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- Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report
- This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees.
- 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."
- An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2
- Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.
- Analysis of Failure of Type 304 Stainless Steel Clad Swaged Powder Fuel Assembly
- From introduction: "The purpose of this report is to describe the observations made during the post-irradiation examination of HPD-2S, and to discuss possible modes of failure.
- 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.
- 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.
- 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."
- An Automatic Analyzing Monitor for Reactor Effluent Cooling Water
- From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."
- Automatic Mass Spectrometer for Isotopic Analysis of Lithium
- Report discussing an improvement program on lithium mass spectrometers.
- Beta-Gamma Dose Rates from U232 in U233
- This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted.
- Chemical Coolants for Machining Uranium in the Presence of Trace Amounts of Chloride
- Discussion of laboratory tests to reduce uranium corrosion.
- 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.
- Chromosomal Aberrations in a Natural Population of Chironomus Tentans Exposed to Chronic Low-Level Environmental Radiation
- From introduction: "Cytological examinations of the irradiated and some unirradiated populations in the radioactive sediments of White Oak Creek and the Clinch River were made."
- 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.
- Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution
- Comparison of the economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO2 nuclear 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.
- Critical Mass Studies of Plutonium Solutions
- Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
- Cubic Spline, a Curve Fitting Routine
- A method of mathematically fitting a curve through a given ordered set of points has been developed and programmed in fortran computer language.
- Design and Economic Evaluation of Fixed Blankets for Fast Reactors
- Report evaluating the design characteristics and limitations of fixed blankets for breeder reactors. This also includes economic considerations for each tested blanket.
- Design and Economic Evaluation of Mobile Blankets for Fast Reactors
- Report evaluating the design characteristics and limitations of mobile blankets for breeder reactors. This also includes economic considerations for each tested blanket. Appendices begin on page 40.
- Design and Installation of a High Precision Temperature and Intimate Contact Monitor for Experimental Vacuum Chucks
- Describes the design criteria, design details, and final installation of a high precision temperature and intimate contact monitor.
- The Design and Performance of Levitation Melting Coils
- The purpose of this study was to provide a means for evaluating the various parameters involved in the design and performance of levitation coils.
- The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results
- From abstract: "This report describes the overall loop design and the means by which this design was developed. These include critical facility measurements, analog computer calculations, hydraulic and heat transfer computations, and the construction and operation of an out-of-pile mock-up loop to determine the dynamic characteristics of the loop."
- Distribution of the Actinide Elements in the Molten System: KCI-AICI3-AI
- Report of data for the distributions of elements 90 through 96 between molten salt solutions of their chlorides and molten aluminum (or alloy) at 725 Celsius.
- Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor
- Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.
- EDP Procedures in Technical Library Operations
- Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
- The Effect of Temperature on the Neutron Attenuation of Magnetite Concrete
- Comparison of experimentally determined relaxation lengths to the value calculated from the concrete composition.
- Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant
- Cycle study performed on a closed loop Brayton cycle incorporating a gas-cooled nuclear reactor, regeneration, and compressor intercooling. The purpose of the study was to determine the effect of various cycle parameters on efficiency and cost.
- An Elliptic Integral Computer Package for Magnetic Fields, Forces, and Mutual Inductances of Axisymmetric Systems, and a Versatile Line-Tracing Routine
- Report describing a set of high-precision routines for the IBM 7090 that perform efficiently the calculations most often required on axially symmetric magnetic systems. The routines compute the vector potential, field components, and the mixed gradient for current systems and for certain idealized distributions of magnetized matter. The programs for the current systems were developed from a set of six equations in elliptic integrals, which suffice when correlations are fully exploited for all the relevant properties of loops and solenoids.
- An Engineering Test Program to Investigate a Loss of Coolant Accident
- From preface: "The purpose of this report is to present an engineering test program for investigating a loss of coolant accident for a pressurized water-cooled and moderated reactor system."
- Engineering Test Reactor Critical Facility Control System Manual
- This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
- Engineering Test Reactor : Engineering Design and Safeguards Report
- From abstract: "Detail and engineering drawings for the Engineering Test Reactor."
- EOCR Control Rod and Driver Fuel Hydraulic Tests
- Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.
- Evaluation of Diethers as Uranium Extractants
- Report on the determination of several physical properties, pertinent to uranium extraction, for a number of ethers and related compounds.
- Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1
- Report discussing the evaluation of the "behavior of austenitic and ferritic stainless steels, iron-chromium-aluminum base alloys and nickel-base superalloys, in medium and high temperature simulated reactor environments" (p. 2).
- Evaluation of Radiation Stabilizers for Terphenyl by High-Temperature Electron Irradiation
- From summary: "Experiments to determine effectiveness of additives to reduce radiolytic damage to a mixture of isometric terphenyls in which 93 separate compounds were evaluated."
- Experimental Stress Analysis of EGCR Pressure Vessel
- Report regarding the structural evaluations made of the upper head of the Experimental Gas Cooled Reactor (EGCR). This report includes descriptions of the model, experimental procedures, and analyses of the results. Appendix begins on page 139.
- Extraction of Thorium Nitrate from Nitric Acid by TBP - "Ultrasene"
- Equilibrium data are presented for the distribution of thorium nitrate and nitric acid between aqueous solutions and tri-n-butyl phosphate diluted with kerosene.
- Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes
- Development of a fabrication process and the manufacture of 95 PRTR process tubes demonstrates that the commercial fabrication of high quality Zircaloy-2 pressure tubing is feasible.
- Factors Affecting Fluidization of Uranium Trioxide Powders
- Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.
- Failure Test of a Double Chambered NaK-Filled Irradiation Capsule
- Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.
- Fast Neutron Data
- A report concerning fast neutrons including theory and compiled data.
- Final Design Report: DR-1 Gas Loop
- Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
- Final Design Report KAPL-120 High Pressure Recirculating Water Loop
- Basic information on the design of the Knolls Atomic Power Laboratory (KAPL) -120 loop.
- Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity
- A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.
- Fire Test of Wooden-Jacket Shield for Radioisotope Shipping Container
- "This report covers fire tests conducted on an experimental design of a wooden-jacket shield for radioisotope shipping containers" (p. i).