Technical Report Archive & Image Library (TRAIL) - 75 Matching Results
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- 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."
- Aerospace Nuclear Safety: October 1 - 4, 1963
- Proceedings on aerospace nuclear safety.
- 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).
- 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.
- 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.
- 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 Reactors Program Annual Progress Report: 1962
- Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
- 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.
- 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.
- Cobalt-60 Bulk Grain Irradiator: Study Report
- Report issued by the Brookhaven National Laboratory discussing bulk grain irradiators. As stated in the abstract, "this report presents the results of a study to conceive, evaluate, review and estimate costs for a number of suitable designs for a Cobalt-60 Bulk Grain Irradiator; select a preferred type; and establish required criteria for future detail design and construction of the selected concept" (p. ii). This report includes tables, and illustrations.
- 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.
- 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.
- 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."
- Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium
- Report regarding "the development of a process suitable for large-scale separation of highly purified promethium from the trivalent fission product rare earth mixture" (p. 3).
- Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor
- Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.
- EDP Procedures in Technical Library Operations
- Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
- 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.
- 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 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."
- An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle
- Report that "describes an investigation of the flow characteristics in a horizontal, converging-diverging nozzle for a two-phase, two-component system" (p. 1) using air and water and "attempting to determine the effects of accelerating the liquid phase by the gaseous phase" (p. 1).
- Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat
- Report describing the development, fabrication, and nondestructive and destructive evaluation of stainless steel-clad fuel plates, the evaluation of fuel subassemblies, and the assembly of fuel element components at Argonne National Laboratory.
- Final Report : Large Reactor Study for Sea Water Distillation
- From introduction: This report presents the results of a study of large nuclear reactor systems for supplying energy for the distillation of sea water.
- Final Summary Report of the Gas-Cooled Reactor Experiment-1
- Report describing the Gas-Cooled Reactor test facility, its ongoing testing and evaluations of a test reactor, and its operating conditions and characteristics.
- Flora of Healthy Dogs: [Part] 2. Isolation of Enteroviruses from Lower Intestines
- Fecal specimens from apparently healthy dogs were inoculated into MK, DK, HeLa, and CP cells. Twenty-six cytopathic agents were isolated in MK, 11 in HeLa, and 4 in CP, but none in DK cells. Neutralization tests indicated that all but one of the viruses were either strains of ECHO type 6 or were closely related to it. Twenty-one of 29 dogs were carrying the virus.
- Fundamentals in the Operation of Nuclear Test Reactors: Volume 2, Materials Testing Reactor Design and Operation
- Second volume of reports on the operation of nuclear test reactors. It includes six chapters: engineering description fo the materials testing reactor, reactor control components and instrumentation, reactor control circuitry, reactor operation, reactor shutdown and tank work, and supplemental facilities at the materials testing reactor.
- 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.
- Gas-Metal Reactions with Iron- and Nickel-Base Heat Resistant Alloys: An Interpretive Literature Survey
- Report reviewing literature that concerns "the compatibility of stainless steels and nickel-base alloys with various gases which might be present in or around a high temperature nuclear reactor" (p. 2).
- The Hanford Isotopes Production Plant Engineering Study
- Report presenting the conceptual design, estimates of capital and operating costs, and details of the operation of a plant "capable of high volume production of encapsulated heat sources" (p. 3) of radioisotopes Sr90, Cs137, Ce144, and Pm147.
- Hanford Radiological Sciences Research and Development Annual Report for 1962
- Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.
- Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1962 - March 1, 1963
- Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
- Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1963 - September 1, 1963
- Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
- Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1963 - June 1, 1963
- Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
- Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1962 - December 1, 1962
- Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
- 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.
- High-Temperature Irradiation of UO₂-BeO Bodies
- From introduction: "Irradiation experiment performed to simulate burnup data under close to reactor temperatures."
- High Temperature Short-Time, Uranium Carbide-Metal Reactions
- Report investigating the compatibility of uranium carbide with tungsten, tantalum, molybdenum, Zircaloy-2, AISI 304L SS, Inconel, Hastelloy F, niobium-1% Zr, and niobium-33% Ta-1% Zr. These pairs were heated together at 1000 C and above for ten minutes.
- ICPP Waste Calcining Facility : Safety Analysis Report
- Report documenting a study "made of the radiological hazards associated with operation of the ICPP Waste Calcination Facility" and contains "[d]etails of the safety analysis and extensive information on the process, equipment, and operation procedures" (p. iii). Each section has its own pagination.
- 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.
- 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-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 3, July 1963 - November 1963
- Report containing the results of a two year program wherein the 85 zircaloy-2 pressure tubes in Hanford Laboratories' Plutonium Recycle Test Reactor (PRTR) were monitored. Experimental procedures and results are described.
- Irradiation Behavior of High Purity Uranium
- Report that "describes the behavior of small, high purity uranium specimens irradiated under controlled conditions" (p. 2).
- 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.
- 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.
- Materials for Superheated Fuel Sheaths: Relative Performance of Alloys in Superheated Steam Environments
- From abstract: "Study of radiation effects upon the tensile properties of the alloys, corrosion behavior in the absence and presence of stress, effect of prolonged, high temperature exposures upon structure sensitive properties of the alloys, and physical metallurgical changes as a function of exposure in a superheat environment.
- A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions
- Report containing a method for beta-gamma counting of hands, shoes, and clothing via an instrument that employs scintillation detectors and solid-state circuits.
- 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.
- 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.