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 Decade: 1960-1969
 Collection: Technical Report Archive and Image Library
Idaho Division Summary Report
Report issued by the Argonne National Laboratory discussing a summary of projects conducted with the Idaho Division. Descriptions of each project are presented. This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc170898/
Idaho Division Summary Report: July, August, September, 1960
Report issued by the Argonne National Laboratory covering a summary report of the work conducted by the Idaho Division. Experimental work and progress made on reactors are presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc170896/
Particle Accelerator Division Summary Report: April Through September 1960
Report issued by the Argonne National Laboratory discussing a summary report of the Particle Accelerator Division. As stated in the summary, "this report outlines two methods applicable respectively to longhand and computer calculations" (p. 4). This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc170890/
Summary of Available Data on the Strontium 90 Content of Foods and of Total Diets in the United States
No Description digital.library.unt.edu/ark:/67531/metadc13122/
Ultramicro Methods in Biochemistry: [Part] 1. General Consideration, [Part] 2. Procedures for the Determination of Serum Bilirubin
No Description digital.library.unt.edu/ark:/67531/metadc13141/
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. digital.library.unt.edu/ark:/67531/metadc100636/
In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962
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. digital.library.unt.edu/ark:/67531/metadc100622/
Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements
Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs. digital.library.unt.edu/ark:/67531/metadc100620/
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. digital.library.unt.edu/ark:/67531/metadc100623/
Fuel Core Tester - UT-2
Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2). digital.library.unt.edu/ark:/67531/metadc100588/
Steam Cooled Power Reactor Evaluation - Beloyarsk (Ural) Reactor
Report evaluating "the effects of nuclear steam superheating, as utilized in the Russian design, on the economics of electric power production, assuming the use of such a design in the United States" (p. 1). This report includes a description of the Beloyarsk Station and modifications made to the Russian designs for use in the United States. digital.library.unt.edu/ark:/67531/metadc100597/
Dissolution of Power Reactor Fuel Cores
Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials. digital.library.unt.edu/ark:/67531/metadc100595/
Hanford Controlled Potential Coulometer
Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23. digital.library.unt.edu/ark:/67531/metadc100593/
Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: August 1960 Through November 1962
Report documenting experience gained by operating the spare PRTR Primary Process Pump. This includes descriptions of equipment used, testing procedures, and operating history. digital.library.unt.edu/ark:/67531/metadc100592/
Hanford Summary Report for the Hanford Plutonium Critical Mass Laboratory
Report that summarizes the potential hazards of the Hanford Critical Mass Laboratory and presents operation procedures which will limit the probability of a nuclear accident. The report also outlines the planned experimental program, descriptions of the facility, and the administration of nuclear safety in the laboratory. digital.library.unt.edu/ark:/67531/metadc100594/
The Thermal Hydraulics Laboratory at Hanford
Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49. digital.library.unt.edu/ark:/67531/metadc100590/
Description of the Thermal Hydraulics Laboratory at Hanford
Report describing the thermal hydraulics facilities at Hanford Laboratories as well as its operation, equipment, and systems. digital.library.unt.edu/ark:/67531/metadc100589/
Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C
Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations. digital.library.unt.edu/ark:/67531/metadc100596/
Molten-Salt Reactor Program Semiannual Progress Report: for Period Ending August 31, 1962
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program. digital.library.unt.edu/ark:/67531/metadc100419/
The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah
Report containing a survey of the radiation from the nuclear ship Savannah in order to determine the dose rate for people aboard. digital.library.unt.edu/ark:/67531/metadc100427/
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969
Report documenting the ongoing research and development of the Oak Ridge National Laboratory's Chemical Technology Division. digital.library.unt.edu/ark:/67531/metadc100472/
Nuclear Energy Centers : Industrial and Agro-Industrial Complexes
Report regarding the use of low cost nuclear power to increase both industrial and agricultural production, especially in developing nations. digital.library.unt.edu/ark:/67531/metadc100496/
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. digital.library.unt.edu/ark:/67531/metadc100428/
Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962
Report issued by Oak Ridge National Laboratory that discusses progress and work performed by the Chemical Technology Division. digital.library.unt.edu/ark:/67531/metadc100411/
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. digital.library.unt.edu/ark:/67531/metadc100424/
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. digital.library.unt.edu/ark:/67531/metadc100433/
Status Report Number Three on Clinch River Study
Report describing the progress made in the Clinch River Study for the period May to October 1961. This report is based off of multiple reports of water sampling conducted across six stations in order to evaluate the safety and radioactive content of the Clinch River. digital.library.unt.edu/ark:/67531/metadc100431/
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. digital.library.unt.edu/ark:/67531/metadc100432/
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. digital.library.unt.edu/ark:/67531/metadc100416/
Development of Fabrication Procedures for Core B Fuel Elements for the Enrico Fermi Fast Breeder Reactor
Report describing the "development procedures for fabricating the proposed Core B fuel element of the Enrico Fermi Fast Breeder Reactor" (p. 1). This includes a description of various components, reactor assembly, and reported conclusions. Appendices begin on page 57. digital.library.unt.edu/ark:/67531/metadc100435/
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. digital.library.unt.edu/ark:/67531/metadc100429/
Procedures for Fabricating Aluminum-Base ATR Fuel Elements
Report concerning the relatively inexpensive fabrication of an aluminum-based fuel element for the Oak Ridge National Laboratory's 250-Mw Advanced Test Reactor. digital.library.unt.edu/ark:/67531/metadc100360/
Maritime Reactor Project Annual Progress Report for Period Ending November 30, 1963
Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Maritime Reactor Program. Progress and studies conducted during 1963 are presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100302/
Microscopic and Autoradiographic Studies of Distribution of Uranium in the Rat Kidney
Report issued by the Oak Ridge National Laboratory discussing studies conducted on uranium retention in rat kidneys. Methods, equipment, and results of the studies are presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100330/
Laboratory Development of Processes for Fixation of High-Level Radioactive Waste in Glassy Solids. [Part] 3, Wastes from the Purex Solvent Extraction Process
Report concerning the fixation and disposal of toxic waste derived from the Purex solvent extraction process. digital.library.unt.edu/ark:/67531/metadc100362/
A Comparative Evaluation of Advanced Converters
Report issued by the Oak Ridge National Laboratory discussing advanced converters. Comparisons of advanced converters are presented. This report includes tables, and illustrations digital.library.unt.edu/ark:/67531/metadc100328/
Interim Report on Corrosion by Zirconium-Base Fluorides
Report issued by the Oak Ridge National Laboratory discussing studies conducted on corrosion by fluorides. Equipment, procedures, results, and analysis is presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100324/
Type 316 Stainless Steel, Inconel, and Haynes Alloy No. 25 Natural-Circulation Boiling-Potassium Corrosion Test Loops
Report issued by the Oak Ridge National Laboratory discussing natural-circulation corrosion test loops. As stated in the abstract, "an investigation was undertaken to determine the compatibility of conventional nickel, iron, and cobalt-base high-temperature alloys with boiling potassium. The tests were designed to obtain quantitative information on the dissolution of the container alloys by condensing potassium and the subsequent deposition of solute in the subcooled liquid region of the test device" (p. 1). This report includes tables, illustrations, and illustrations. digital.library.unt.edu/ark:/67531/metadc100335/
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965
Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100305/
Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums
Report issued by the Oak Ridge National Laboratory discussing the evaporation of alloys in high vacuums. As stated in the introduction, "the investigation encompasses measurements of the evaporation rates, identification of the evaporating elements, and correlation of these measurements to the alloy composition for specimens in both the polished and oxidized conditions" (p. 2). This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100327/
High-Density Concrete for Gamma and Neutron Attenuation
Report issued by the Oak Ridge National Laboratory discussing the development of a high-density concrete. As stated in the abstract, "the basic approach to high-density concrete mix design is reviewed to show that theoretical calculations for concrete mixes do give results that are reliable" (p. 1). This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100331/
Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor
Report issued by the Oak Ridge National Laboratory discussing irradiation testing of fast breeder reactors. As stated in the introduction, "it is the purpose of this report to describe the irradiation studies carried out in support of the Core B fuel element development program" (p. 3). This report includes tables, illustrations, and photographs. digital.library.unt.edu/ark:/67531/metadc100332/
Thermodynamic Calculations Relating to Chloride Volatility Processing of Nuclear Fuels: [Part] 2. The Capacity of Chlorine for Transporting Plutonium Tetrachloride Vapor During Reaction of U3O8-PuO2 with Carbon Tetrachloride
Report issued by the Oak Ridge National Laboratory discussing thermodynamic calculations of nuclear fuels. As stated in the introduction, "the equations developed in this report could be used to calculate the capacity of chlorine for transporting plutonium tetrachloride" (p. 2). This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc100329/
An Experimental Investigation of Instantaneous-Collapse and Creep-Buckling Characteristics of Cylindrical Shells
Report tests "conducted on nominal 8.0-in.-OD by 0.25-in.-wall and 4.0-in.-OD by 0.12-in.-wall specimens made from commercial pipe and tubing" (p. 1). digital.library.unt.edu/ark:/67531/metadc100352/
Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV
Report issued by the Oak Ridge National Laboratory discussing techniques to obtain measurements of alpha for enriched uranium. Descriptions of equipment and experiments used to obtain alpha are presented. This report includes tables, and illustrations. digital.library.unt.edu/ark:/67531/metadc100333/
Civil Defense Research Project Annual Progress Report: March 1966 - March 1967
Report containing the results of Oak Ridge National Laboratory's research relating to civil defense. digital.library.unt.edu/ark:/67531/metadc100473/
Computer Programs Using Zonal Harmonics for Magnetic Properties of Current Systems with Special Reference to the IBM 7090
Report that "discusses the magnetic vector and scalar potentials, magnetic field components and their derivatives, and flux linkage for single current systems, and the mutual inductance, forces and torques between two such systems, whose axes are coplanar but not necessarily coincident" (p. 1). digital.library.unt.edu/ark:/67531/metadc100425/
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. digital.library.unt.edu/ark:/67531/metadc100412/
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. digital.library.unt.edu/ark:/67531/metadc100635/
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H
Report describing the fabrication of of the I-H aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR), including the materials used and design specifications. Appendix begins on page 28. digital.library.unt.edu/ark:/67531/metadc100605/
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