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Irradiation Effects in the EGCR Fuel

Description: From foreword: "This is a documentation of the experiments performed and the data accumulated during the early period of the Experimental Gas-Cooled Reactor (EGCR) fuel element design."
Date: June 1965
Creator: Baumann, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Shielding of Mobile Reactors - [Part] 2

Description: From abstract: "The methods of applying results of bulk-shielding measurements to the design of reactor shields is outlined. Geometrical transformations for the more common shapes are derived, as are approximate means of calculating leakage of radiation. As an illustration of the methods, the ORNL Lid Tanks and Bulk Shielding Facility data are transformed to a standard geometry and compared. Two direct calculations of water attenuation, using cross sections described in the previous article, ar… more
Date: June 30, 1952
Creator: Blizard, E. P. & Welton, T. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Investigation of ThF4 - Fused Salt Solutions for Homogeneous Breeder Reactors

Description: Technical report presenting a consideration of the characteristics of fused salt-ThF4 solutions suitable for use in homogeneous reactors. Presented in tandem with a brief survey of the literature pertaining to such solutions and a summary of the experimental work accomplished. [From Abstract]
Date: June 19, 1951
Creator: Blomeke, J. O. & Johnston, C. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Instrumentation and Controls Division Annual Progress Report for the Period Ending September 1, 1966

Description: Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Instrumentation and Controls Division during 1966. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: June 1967
Creator: Borkowski, C. J.; Dandl, R. A.; Epler, E. P. & Harrill, C. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965

Description: 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.
Date: June 1965
Creator: Briggs, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electron Metallography of Pyrolytic Carbon Coatings on Fuel Particles

Description: A replica electron microscope study of as-polished and cathodically etched surfaces of pyrolytic carbon coating on fuel particles has been made in an attempt to characterize coatings that showed as much as a 30% difference in bult density. High and low density coating could be characterized by their polished surface textures; however, these features were not indicative of the true structure as seen by direct electron transmission. Microvoids detected by the transmission study of cleavage flakes… more
Date: June 1964
Creator: Dubose, C. K. H. & Stiegler, J. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Solution Critical Experiments for the High-Flux Isotope Reactor

Description: Report containing experiments conducted at the Oak Ridge National Laboratory's Critical Experiments Facility. These experiments involved "determining the critical parameters of the assembly with varying amounts of neutron absorber in the D20 reflector, measuring the relative neutron flux distribution for various conditions of reflector poison and fissile solution concentration, determining the ratio of the absolute thermal-neutron flux in the center of the assembly to the power in the fissile s… more
Date: June 12, 1963
Creator: Fox, J. K.; Magnuson, D. W. & Gilley, L. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Forced Convection Heat Transfer in Thermal Entrance Regions Part III. Heat Transfer to Liquid Metals

Description: Technical report covering the work done to explore heat transfer analytically and experimentally in liquid metals in turbulent flow within the thermal entrance region of circular tubes having uniform well temperature. Includes implications of this research. [From Summary]
Date: June 25, 1954
Creator: Harrison, William B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Type 316 Stainless Steel, Inconel, and Haynes Alloy No. 25 Natural-Circulation Boiling-Potassium Corrosion Test Loops

Description: 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 d… more
Date: June 1965
Creator: Jansen, D. H. & Hoffman, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C

Description: 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.
Date: June 10, 1963
Creator: Jenks, G. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending March 10, 1956

Description: This quarterly progress report of the Aircraft Nuclear Propulsion Project at ORNL records the technical progress of the research on circulating-fuel reactors and ether ANP research at the Laboratory under its Contract W-7405-eng-26. The report is divided into three major parts: I. Reactor Theory, Component Development, and Construction, II. Materials Research, and III. Shielding Research.
Date: June 13, 1956
Creator: Jordan, W. H.; Cromer, S. J. & Miller, A. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia

Description: From abstract: "The Darex process developed for the recovery of uranium from stainless steel-containing reactor fuels consists of three steps: (1) dissolution of the fuel material in dilute aqua regia, (2) removal of chloride from the solution to prevent corrosion of downstream stainless steel process equipment, and (3) adjustment of the nitrate solution to solvent extraction feed conditions."
Date: June 7, 1962
Creator: Kitts, F. G. & Clark, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electronuclear Research Division Semiannual Progress Report For Period Ending March 20, 1955

Description: The ORNL 86-in. cyclotron is being modified to provide for deflection of the proton beam. It is expected that operation will be resumed late in the spring. Nuclear physics work was limited, for the most part, to interpretation of previously collected data and to making preparations for utilizing the deflected beam. It was found that for certain isotopes the production rates could be almost doubled by operating at a slightly reduced energy and a much larger current. With the use of the ORNL 63-i… more
Date: June 24, 1955
Creator: Livingston, Robert S. & Howard, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Semiannual Progress Report for Period Ending October 10, 1955

Description: Progress report of the Oak Ridge National Laboratory Metallurgy Division providing updates on various projects, experiments, and other work. This report includes a summary of nondestructive testing, physical chemistry of corrosion, fundamental physico-metallurgical research, HRP metallurgy, process metallurgy, metallurgical materials and processing, metallography, and ceramics research.
Date: June 14, 1954
Creator: Manly, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRP Radiation Corrosion Studies: In-Pile Loop L-4-11

Description: Report issued by the Oak Ridge National Laboratory discussing radiation corrosion studies. As stated in the introduction, "the purpose of this experiment was to compare the performance of a large number of materials under similar irradiation and exposure conditions" (p. 1). This report includes tables, illustrations, and photographs.
Date: June 27, 1958
Creator: McWherter, J. R. & Baker, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Metallurgy Division Quarterly Progress Report for Period Ending January 31, 1951

Description: Technical report covering the metallurgy of thorium and on fabrication techniques. Report investigates the stability and corrosion resistance of thorium exposed to eutectic NaK, extrusion as a means of fabrication of thorium tubes or rods, and corrosion of large single metal crystals by liquid metals. [From Summary]
Date: June 7, 1951
Creator: Miller, E. C. & Bridges, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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