Latest content added for UNT Digital Libraryhttps://digital.library.unt.edu/search/?t=fulltext&fq=str_title_serial%3AUC+%28Series%29&display=grid&sort=date_a2015-01-19T05:58:23-06:00UNT LibrariesThis is a custom feed for searching UNT Digital LibraryAnalytical Chemistry Division Annual Progress Report, December 31, 19602014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100439/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100439/"><img alt="Analytical Chemistry Division Annual Progress Report, December 31, 1960" title="Analytical Chemistry Division Annual Progress Report, December 31, 1960" src="https://digital.library.unt.edu/ark:/67531/metadc100439/small/"/></a></p><p>Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.</p>Experimental Stress Analysis of EGCR Pressure Vessel2014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100402/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100402/"><img alt="Experimental Stress Analysis of EGCR Pressure Vessel" title="Experimental Stress Analysis of EGCR Pressure Vessel" src="https://digital.library.unt.edu/ark:/67531/metadc100402/small/"/></a></p><p>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.</p>Superposition of Forced and Diffusive Flow in a Large-Pore Graphite2014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100458/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100458/"><img alt="Superposition of Forced and Diffusive Flow in a Large-Pore Graphite" title="Superposition of Forced and Diffusive Flow in a Large-Pore Graphite" src="https://digital.library.unt.edu/ark:/67531/metadc100458/small/"/></a></p><p>Report describing an "investigation of steady-state counter-flow of gases in a large pore graphite" by exposing it to streams of helium and argon.</p>Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 12014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100598/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100598/"><img alt="Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1" title="Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1" src="https://digital.library.unt.edu/ark:/67531/metadc100598/small/"/></a></p><p>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).</p>Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 19602014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100392/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100392/"><img alt="Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960" title="Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960" src="https://digital.library.unt.edu/ark:/67531/metadc100392/small/"/></a></p><p>Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.</p>Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 19602013-09-20T16:38:33-05:00https://digital.library.unt.edu/ark:/67531/metadc67301/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc67301/"><img alt="Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960" title="Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960" src="https://digital.library.unt.edu/ark:/67531/metadc67301/small/"/></a></p><p>Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.</p>Final Design Report: DR-1 Gas Loop2015-01-19T05:58:23-06:00https://digital.library.unt.edu/ark:/67531/metadc100603/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100603/"><img alt="Final Design Report: DR-1 Gas Loop" title="Final Design Report: DR-1 Gas Loop" src="https://digital.library.unt.edu/ark:/67531/metadc100603/small/"/></a></p><p>Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.</p>Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G2014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100604/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100604/"><img alt="Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G" title="Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G" src="https://digital.library.unt.edu/ark:/67531/metadc100604/small/"/></a></p><p>Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).</p>Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H2014-01-31T11:57:08-06:00https://digital.library.unt.edu/ark:/67531/metadc100605/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100605/"><img alt="Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H" title="Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H" src="https://digital.library.unt.edu/ark:/67531/metadc100605/small/"/></a></p><p>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.</p>Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements2014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100608/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100608/"><img alt="Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements" title="Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements" src="https://digital.library.unt.edu/ark:/67531/metadc100608/small/"/></a></p><p>This report summarizes only that portion of the injection-casting experiments in which the castings were made with air pressure.</p>Mathematics Panel: Annual Progress Report for Period Ending December 31, 19602014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100445/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100445/"><img alt="Mathematics Panel: Annual Progress Report for Period Ending December 31, 1960" title="Mathematics Panel: Annual Progress Report for Period Ending December 31, 1960" src="https://digital.library.unt.edu/ark:/67531/metadc100445/small/"/></a></p><p>Programming research in the construction of a translator to Oracle language from ALGOL.</p>Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor2014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100460/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100460/"><img alt="Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor" title="Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor" src="https://digital.library.unt.edu/ark:/67531/metadc100460/small/"/></a></p><p>Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.</p>Thermonuclear Division Semiannual Progress Report, January 31, 19612014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100450/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100450/"><img alt="Thermonuclear Division Semiannual Progress Report, January 31, 1961" title="Thermonuclear Division Semiannual Progress Report, January 31, 1961" src="https://digital.library.unt.edu/ark:/67531/metadc100450/small/"/></a></p><p>Report describing ongoing progress made at the Oak Ridge National Laboratory's Thermonuclear Division.</p>Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor2014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100601/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100601/"><img alt="Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor" title="Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor" src="https://digital.library.unt.edu/ark:/67531/metadc100601/small/"/></a></p><p>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.</p>Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility2014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100586/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100586/"><img alt="Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility" title="Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility" src="https://digital.library.unt.edu/ark:/67531/metadc100586/small/"/></a></p><p>A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.</p>Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy2014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100609/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100609/"><img alt="Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy" title="Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy" src="https://digital.library.unt.edu/ark:/67531/metadc100609/small/"/></a></p><p>This purpose of this report is to establish a means of determining the mean effective temperature at which any specimen of Al-Si had been annealed.</p>Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 19612014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100447/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100447/"><img alt="Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961" title="Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961" src="https://digital.library.unt.edu/ark:/67531/metadc100447/small/"/></a></p><p>Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.</p>The RBU Reactor-Burnup Code: Formulation and Operation Procedures2014-01-31T11:57:08-06:00https://digital.library.unt.edu/ark:/67531/metadc100611/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100611/"><img alt="The RBU Reactor-Burnup Code: Formulation and Operation Procedures" title="The RBU Reactor-Burnup Code: Formulation and Operation Procedures" src="https://digital.library.unt.edu/ark:/67531/metadc100611/small/"/></a></p><p>Report discussing the computer program RBU, which calculates the neutron, reactivity, and isotopic history of a nuclear reactor in such a way as to facilitate the predictions of fuel costs and reactor performance. This report documents RBU's various calculations and operating procedures.</p>Numerical Results for EGCR Moderator-Element Stress Problems2015-01-19T05:58:23-06:00https://digital.library.unt.edu/ark:/67531/metadc100827/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100827/"><img alt="Numerical Results for EGCR Moderator-Element Stress Problems" title="Numerical Results for EGCR Moderator-Element Stress Problems" src="https://digital.library.unt.edu/ark:/67531/metadc100827/small/"/></a></p><p>From introduction: "A recent report describes the development of a general program for the IBM Type 7090 electronic computer for calculating plane thermal stresses."</p>Inline Densimeter for Pulsed Column Liquid Density Pulse Amplitude, and Pulse Frequency Measurements2014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100462/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100462/"><img alt="Inline Densimeter for Pulsed Column Liquid Density Pulse Amplitude, and Pulse Frequency Measurements" title="Inline Densimeter for Pulsed Column Liquid Density Pulse Amplitude, and Pulse Frequency Measurements" src="https://digital.library.unt.edu/ark:/67531/metadc100462/small/"/></a></p><p>Laboratory fabrication and testing of an inline densimeter.</p>Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 19612014-01-31T11:57:08-06:00https://digital.library.unt.edu/ark:/67531/metadc67302/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc67302/"><img alt="Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961" title="Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961" src="https://digital.library.unt.edu/ark:/67531/metadc67302/small/"/></a></p><p>Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations.</p>Failure Test of a Double Chambered NaK-Filled Irradiation Capsule2015-01-19T05:58:23-06:00https://digital.library.unt.edu/ark:/67531/metadc100599/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100599/"><img alt="Failure Test of a Double Chambered NaK-Filled Irradiation Capsule" title="Failure Test of a Double Chambered NaK-Filled Irradiation Capsule" src="https://digital.library.unt.edu/ark:/67531/metadc100599/small/"/></a></p><p>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.</p>Chemical Technology Division Annual Progress Report, May 31, 19612014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100389/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100389/"><img alt="Chemical Technology Division Annual Progress Report, May 31, 1961" title="Chemical Technology Division Annual Progress Report, May 31, 1961" src="https://digital.library.unt.edu/ark:/67531/metadc100389/small/"/></a></p><p>Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.</p>Evaluation of Ultimate Disposal Methods for Liquid and Solid Radioactive Wastes: Part 2, Conversion to Solid by Pot Calcination2014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100466/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100466/"><img alt="Evaluation of Ultimate Disposal Methods for Liquid and Solid Radioactive Wastes: Part 2, Conversion to Solid by Pot Calcination" title="Evaluation of Ultimate Disposal Methods for Liquid and Solid Radioactive Wastes: Part 2, Conversion to Solid by Pot Calcination" src="https://digital.library.unt.edu/ark:/67531/metadc100466/small/"/></a></p><p>Economic and hazards calculation of pot calcination of Purex and Thorex wastes.</p>Health Physics Division Annual Progress Report, July 31, 19612014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100390/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100390/"><img alt="Health Physics Division Annual Progress Report, July 31, 1961" title="Health Physics Division Annual Progress Report, July 31, 1961" src="https://digital.library.unt.edu/ark:/67531/metadc100390/small/"/></a></p><p>Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.</p>The Thermal Hydraulics Laboratory at Hanford2014-01-31T11:57:08-06:00https://digital.library.unt.edu/ark:/67531/metadc100590/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100590/"><img alt="The Thermal Hydraulics Laboratory at Hanford" title="The Thermal Hydraulics Laboratory at Hanford" src="https://digital.library.unt.edu/ark:/67531/metadc100590/small/"/></a></p><p>Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.</p>Spectral Shift Control Reactor Design and Economic Study2014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc101005/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc101005/"><img alt="Spectral Shift Control Reactor Design and Economic Study" title="Spectral Shift Control Reactor Design and Economic Study" src="https://digital.library.unt.edu/ark:/67531/metadc101005/small/"/></a></p><p>Study of nuclear power plants incorporating the Spectral Shift Control Reactor (SSCR).</p>Large-Scale Slurry-Circulation System, 300-SM2014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100465/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100465/"><img alt="Large-Scale Slurry-Circulation System, 300-SM" title="Large-Scale Slurry-Circulation System, 300-SM" src="https://digital.library.unt.edu/ark:/67531/metadc100465/small/"/></a></p><p>Design philosophy, status of component development, operational procedures, and limitations of each section of the Oak Ridge large-scale, high-temperature, thoria slurry facility.</p>