Technical Report Archive & Image Library (TRAIL) - 766 Matching Results
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- High-Level Radioactive Waste Management Alternatives Section 4: Geologic Disoposal
- From foreword: "This report is a comprehensive overview study of potential alternative methods for long-term management of high-level radioactive waste...Disposal in terrestrial locations."
- Spark-Source Mass Spectrometric Analysis of Common and Radiogenic Lead
- Analysis that is fast and has extremely low levels of detection for more than forty elements that may be present in lead.
- Chemical Coolants for Machining Uranium in the Presence of Trace Amounts of Chloride
- Discussion of laboratory tests to reduce uranium corrosion.
- X-Ray Fluorescence Tables: Program Description
- Report discussing the mechanics of X-Ray and COMBO computer programs.
- Welded Repair of Fill and Drain Holes in High-Carbon Steel Gas Storage Cylinders
- Report discussing the results of fill and drain holes for hydrostatic pressure tests on head knuckle radius of forged-steel gas storage cylinders.
- Pressure Intensification Provided by External Pressure on a Cylinder Composed of Four Anvils
- Results of experimental investigation for improving intensification and to reduce stress concentrations for anvil redesign.
- Stress Corrosion Cracking in Uranium-Molybdenum Alloys
- Investigation conducted to determine the cause of cracking, during tension, on the surface of tensile specimens of uranium-molybdenum alloys.
- A Versatile Spectrometer Magnet Power Supply
- Early results from actual laboratory operation of a more versatile magnet supply.
- 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.
- Salt Bath Heat Transfer Rates for Uranium Plate
- Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
- 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.
- 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.
- High-Level Radioactive Waste Management Alternatives Section 1: Summary, Section 2: Background and Data Base, Section 3: Evaluation Methodology
- From foreword: "This report is a comprehensive overview study of potential alternative methods for long-term management of high-level radioactive waste."
- Metallurgy Research Operation: Quarterly Progress Report, January - March 1965
- Quarterly progress report on a project to test the radiation effects on metallurgy.
- Fast Flux Test Facility Studies Progress Report: April 1965
- From abstract: "...limited study work was performed on the conceptual design of the proposed fast flux test facility and information was obtained in important areas of supporting technology."
- A Sequence for Predicting Waste Transport by Ground Water
- From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
- Geophysical Seismic Evaluation Study at Hanford
- From introduction: "In June, 1963, a geophysical research program was conducted at Hanford to determine the feasibility and desirability of using seismic methods in geohydrologic studies. Detection and delineation were desired of seven different geological features that in some sites affect the movement of liquid radioactive wastes discharged to the ground."
- Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel
- The experiments described in this report were performed for two purposes: (1) to find a chemical, or combination of chemicals, that would be effective for inhibiting corrosion of steel in static portions of the Hanford water systems, and (2) as screening tests to select candidate mixtures for further testing to replace sodium dichromate as the inhibitor of aluminum and steel corrosion in the Hanford single-pass reactor cooling water.
- INDEX: a Computer Program for Indexing X-ray Diffraction Powder Patterns
- From introduction: "...a logical system has been developed to yield rapidly the indexing of a given powder pattern by using an electronic computer."
- PRTR second generation shim assembly
- From introduction: "This document discusses the design, fabrication, assembly, and testing of a second generation shim rod assembly, and testing of a second generation shim rod assembly prototype for use in the Plutonium Recycle Test Reactor."
- Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development
- First part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. I-ii).
- Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies
- Second part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. II-i).
- Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients
- Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
- Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept
- Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
- Liquid Metal Fast Breeder Reactor Design Study
- From introduction: "The primary objective of the present study was to develop a conceptual design of a large sodium cooled fast breeder reactor of a nominal electrical rating of 1000 Mw operating on the uranium-plutonium cycle."
- SL-1 Annual Operating Report: February, 1960-January 3, [1961]
- The Stationary Low Power Reactor No. 1 (SL-1) was a boiling water reactor demonstration plant for remote military bases. The plant had been operated by Combustion Engineering, Inc. from February, l959 until January 3, 1961 at which time a nuclear excursion rendered the plant inoperable, This report summarizes the of operations of maintenance, test, health and safety, and administrative activities for the year February, 1960 until the incident.
- Ionic Equilibria and Anion Exchange of Uranyl Sulfate Solutions
- Theoretical investigation on the nature of ion exchange of acidified uranyl sulfate solutions with Dowex 21K, a strong base ion exchange resin.
- 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.
- Automatic Mass Spectrometer for Isotopic Analysis of Lithium
- Report discussing an improvement program on lithium mass spectrometers.
- 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.
- 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.
- 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.
- Transistorized Pulse Counting Equipment
- This instrument was designed primarily to meet the need for radiation monitoring equipment in chemical process areas where corrosive vapors exist.
- The Influence of Design and Production Parameters on Fabrication Costs of Nuclear Reactor Fuel Elements
- The objectives for this study were to determine fuel fabrication and assembly costs in a large nuclear power industry for several reactors, fuel rod sizes, and fuel materials.
- An Investigation of a "Dynamic" Theory for Mass Transfer
- A new theory is proposed to evaluate individual mass-transfer coefficients without actual experiment.
- A Continuous Water Monitor for Detecting PPM Quantities of Alkali Metals
- Abstract: "This report describes a flame photometric system which continuously monitors a process water stream for ppm quantities of alkali metals, and automatically diverts the stream when the contamination exceeds a pre-determined level."
- Shipboard Cobalt-60 Radiopasteurizer for Marine Products
- Report issued by the Brookhaven National Laboratory discussing the shipboard cobalt-60 irradiator. As stated in the introduction, "this report discusses the conceptual design of a cobalt-60 shipboard irradiator for use to improve the keeping quality of fish landed aboard commercial fishing trawlers operating out of ports along the eastern seaboard of the commercial United States" (p. 1). This report includes tables, and illustrations.
- Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies
- Report describing a pilot plant constructed at Argonne National Laboratory for studying two major process steps for the recovery of uranium and plutonium from spent nuclear fuels of power reactors. A major objective is the demonstration of optimum process conditions for the two steps for synthetic reactor fuel compositions, including those containing mixtures of inactive fission products.
- Potential Applications of Nuclear Energy for Process and Space Heat in the United States
- A survey and analysis of the potential opportunity for the use of nuclear reactors to satisfy process and space heat requirements in the continental United States and Alaska has been completed. The greatest emphasis has been devoted to manufacturing industries that utilize large quantities of process heat.
- A Technical and Economic Evaluation of Solid-Fuel Gasification using Nuclear Heat: Production of Pipeline Gas, Liquid Fuels, and Chemicals from Lignite and Bituminous Coal
- From abstract: Results are reported of a study to determine the most economical method of utilizing nuclear heat to gasify a North Dakota lignite and a West Virginia bituminous coal so that the resulting gas is suitable as a source of synthesis gas for fuels and chemicals.
- The Design Study of Fluid Engine Power Systems
- From abstract: This report presents information generated during a six month feasibility study of an engine which uses a supercritical working fluid as the secondary portion of nuclear powered electric generating system.
- A Nuclear Reactor System for Generating Power and Supplying Steam to a Water Desalination Plant in the Florida Keys
- From foreword: The results of an engineering study directed toward the evaluation and selection of a nuclear reactor system designed to produce electricity and furnish steam to a water desalination plant in the Florida Keys are given in this report.
- Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin
- Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
- Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin
- Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
- The Ductility of Brazed Stainless Steel Joints
- Abstract: "The ductility of Type 310 stainless steel T-joints brazed with GE-62 brazing alloy was measured at room temperatures 1200, 1650, and 1800 F. The measure of ductility was taken as the plastic axial strain required to crack braze fillets in T-section tensile specimens. At elevated temperatures, the ductility of as-brazed joints approximated that of the stainless steel, but at room temperature the brazed joints had only one-tenth the ductility of the base metal. Annealing for 16 hr at 1800 F in air was found to triple the room-temperature ductility of the brazed joint."
- The Effect of Copper, Nickel, Iron, and Chromium on the Tensile Properties of Preferentially Oriented Beryllium Sheet
- From abstract: The planes and modes of fracture as a result of the mixture of beryllium and other elements were investigated.
- Fundamental and Applied Research and Development in Metallurgy: Conceptual Design of a U-233 Fuel Refabrication Plant
- From abstract: A preliminary study has been made of a direct access, streamlined process for the rapid fabrication of fuel using uranium-233.
- Feed Materials Production Center Summary Technical Report: January 1, 1963-March 31, 1963
- This is a summary report of various technical projects relating to uranium.
- Feed Materials Production Center Summary Technical Report: July 1, 1963-September 30, 1963
- From abstract: The temperature of molten uranium was measured indirectly by an infrared radiation pyrometer. The emissivities of graphite and molten uranium were determined, and a series of equations correlating pyrometer readings with melt temperatures was derived.
- Feed Materials Production Center Summary Technical Report: April 1, 1963-June 30, 1963
- This report summarizes several reports pertaining to uranium processing.