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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.
Effect of Explosive Impacting on Uranium
Abstract: The tensile and yield strengths of both cast and wrought uranium discs were substantially increased by explosively impacting them at room temperature and at 375 deg F. However, the room-temperature impacting caused gross damage in the cast material and slight internal damage in the wrought material at the highest impacting pressures. Impacting at 375 deg F, which is just above the brittle-ductile transition temperature for uranium, was the most effective method for increasing the strengths with no damage to either the cast or wrought material. This impacted material retained some of its increased strength after a low temperature (425 deg C) vacuum anneal that greatly increased the elongation. A salt anneal caused a partial recrystallization in the impacted cast uranium. (auth).
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.
International Symposium on Developments in Irradiation Capsule Technology: Held at Pleasanton, California, May 3-5, 1966
Assembled papers regarding advances in irradiation capsule technology.
Experimental Radiation Measurements in Conventional Structures: Part 1, Radiation Measurements in Two Two-Story and Three One-Story Typical Residential Structures Before and After Modification
Report discussing the methods, data, and analysis of results for "An experimental study designed to provide a basis for estimating protection against fallout radiation " (p. v) using one- and two-story structures with basements.
Aerial Radiological Monitoring System Part 4: Equipment and Procedures Through Fiscal Year 1966
From abstract: "This report describes the Aerial Radiological Measuring System (ARMS-II) operated by EG&G, Inc., for the Division of Biology and Medicine, U. S. Atomic Energy Commission."
Determining the "State of Charge" of Nickel-Cadmium Batteries by Farad Capacitance Measurements
From abstract: "A rapid simple method has been developed for determining state of charge of the widely used nickel-cadium rechargeable battery. The method described is based on the experimentally verified relationship between farad capacitance and state of charge."
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 4. Steam Driven Coolant Pumps
Fourth 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).
The Development and Testing of UO2 Fuel Systems for Water Reactor Applications: Summary Report, July 1, 1961 - June 15, 1962
From introduction: "The work described in this report represents the Joint United States - European Atomic Energy Community effort which is in keeping with the spirit of cooperation in contributing to the common good by the sharing of scientific and technical information and minimizing the duplication of effort by the limited pool of technical talent available in Western Europe and the United States."
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.
Proceedings of the Symposium on the Solidification and Long-Term Storage of Highly Radioactive Wastes: February 14-18, 1966, Richland, Washington
Symposium proceedings regarding long-term storage of highly radioactive wastes resulting from nuclear reactors.
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.
FUDGE 4A: A Computer Program for Gamma Dose Rate Distribution from Rectangular Sources
Report issued by the Brookhaven National Laboratory discussing the recently modified FUDGE 4A computer program. As stated in the introduction, "this report presents the details and technical information required for the proper use of FUDGE 4A" (p. 1). This report includes tables, and illustrations.
High-Pressure Gamma Loop for Brookhaven National Laboratory
Report issued by the Brookhaven National Laboratory discussing high-pressured gamma loops. As stated in the introduction, "this latest endeavor involved three test cells, a gamma irradiation pool and supporting equipment, as well as an enlarged high-pressure gamma loop facility" (p. 1). This report includes tables, and illustrations.
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.
Brookhaven National Laboratory Annual Report: 1961
Report issued by the Brookhaven National Laboratory discussing annual work conducted during 1961. As stated in the introduction, "the progress and trends of the research program are presented together with a description of the operational, service, and administrative activities of the Laboratory" (p. ix). This report includes tables, illustrations, and photographs.
Cold-Mold Arc Melting and Casting
Report issued by the U.S. Bureau of Mines providing updates and additional information related to cold-mold arc melting and casting. Abstract: "This bulletin reviews the historical background of the cold-mold arc-melting technology, with specific references to the development that led to homogeneous zirconium ingots. Descriptions are given of modern production arc-furnaces for vacuum melting of both exotic and conventional metals. Besides zirconium, specific data are given for production of chromium, thorium, and copper. The development of the skull-casting technique for titanium is detailed, and the application of the technique to such refractory metals as molybdenum and tungsten is described. Factors of operation of the apparatus and furnace design are considered" (p. 1).
Irradiation Testing of Enrico Fermi Prototype Fuel Pins in the CP-5, 1957-1959
Report issued by the APDA over studies conducted on the irradiation of fuel pins in nuclear reactors. As stated in the introduction, "results of these tests have verified predicted high-temperature allowable burn-ups and showed that under certain conditions, excessive swelling could occur at low temperatures" (p. 5). This report includes tables, illustrations, and photographs.
The Doppler Effect in Fast Neutron Reactors
Report issued by the APDA over studies conducted on the Doppler Effect in fast neutron reactors. Methods and results of the studies are presented and discussed. This report includes tables, and illustrations.
HAFEVER: An Inelastic Scattering Code for the IBM 704 Computer
Report issued by the APDA over HAFEVER, a code developed for the IBM 704 computer. As stated in the introduction, "HAFEVER is an IBM 704 code which calculates the energy exchange inelastic scattering cross section" (p. 3). Descriptions of the code and the theory behind the code are discussed. This report includes tables.
Removal of Sodium from Core Subassemblies with White Oil and Ultrasonics
Report issued by the APDA over methods "for removing sodium from fuel and blanket sub-assemblies that have been irradiated in the reactor of the Enrico Fermi Atomic Power Plant" (p. 3). The cleaning methods are described, as well as experimental studies conducted on them. This report includes illustrations, and photographs.
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