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Surface Sample Site Locations in the Aiken County Study Area
Maps showing the location of surface sample collection sites in the Aiken County National Uranium Resource Evaluation Program (NURE) study area, along with maps showing the alkalinity, conductivity, and pH in surface water in the site collection areas.
Date:
November 1983
Creator:
Thayer, Paul A.
Object Type:
Dataset
System:
The UNT Digital Library
Appendix E-4: Aiken Scintillometer Maps
Maps showing site locations and symbol plots for eU, eTh, and eU/eTh for the area of Aiken County, South Carolina surveyed for a National Uranium Resource Evaluation Program (NURE) exploration report.
Date:
November 1983
Creator:
Thayer, Paul A.
Object Type:
Map
System:
The UNT Digital Library
Appendix E-3: Aiken Scintillometer Data
Tables presenting scintillometer data for quadrangles surveyed near Aiken County, South Carolina, for a National Uranium Resource Evaluation Program (NURE) exploration report.
Date:
November 1983
Creator:
Thayer, Paul A.
Object Type:
Dataset
System:
The UNT Digital Library
Appendix E-2: Aiken Soil Survey Results
Tables presenting data from a soil survey conducted for a National Uranium Resource Evaluation Program (NURE) exploration of Aiken and Lexington County, South Carolina. "The table begins with the soil sample number. Other entries are Po-210 (pico curies per gram), U (ppm), surface area (S.A.) (in square meters per gram), Po-210/U, and Po-210/S.A. x 100. Also in Appendix E-2 are histograms and cumulative frequency plots of 1) Log U, 2) Log Po-210 x 100 (multiplied by 100 for convenience), 3) Log (Po-210/U), and 4) Log (Po-210/S.A. x U). A site location map, as well as symbol plot maps of U, Po-210 x 100, and Po-210/S.A. x U, are also in Appendix E-2." (p. E-11 of report)
Date:
November 1983
Creator:
Scienterra, Inc.
Object Type:
Dataset
System:
The UNT Digital Library
Appendix E-1: Akien Hydrocarbon Data
Tables presenting the results of analyses for light hydrocarbons in ground water samples ordered by site number, providing the location for each.
Date:
November 1983
Creator:
Thayer, Paul A.
Object Type:
Dataset
System:
The UNT Digital Library
Appendix D-2: Graphic Lithologic Logs fo Aiken County Cores
Reports providing a graphic lithologic description of 23 core holes drilled for a National Uranium Resource Evaluation Program (NURE) exploration of Aiken and Lexington County, South Carolina. Gammy ray logs are plotted alongside the graphic lithologic description for each core.
Date:
November 1983
Creator:
Thayer, Paul A.
Object Type:
Report
System:
The UNT Digital Library
Appendix D-1: Geologic Logs of Aiken County Cores
Reports describing the geologic features of 23 core holes drilled for a National Uranium Resource Evaluation Program (NURE) exploration of Aiken and Lexington County, South Carolina. Details provided in each log, in addition to descriptions of the geologic features, include the location, elevation, and date for each drilled core hole.
Date:
November 1983
Creator:
Thayer, Paul A.
Object Type:
Report
System:
The UNT Digital Library
Appendix B-1. Outcrop and Core Descriptions
Reports providing descriptions of outcrops (surface visible rock formations), including locations, elevation, and composition descriptions, surveyed for a National Uranium Resource Evaluation Program (NURE) exploration of Aiken and Lexington County, South Carolina.
Date:
November 1983
Creator:
Thayer, Paul A.
Object Type:
Report
System:
The UNT Digital Library
Appendix B-2: 1:24,000 Geologic Maps of Aiken County, South Carolina
Twenty-eight maps detailing the geologic features of quadrangles within Aiken County, South Carolina. Scale 1:24,000
Date:
November 1983
Creator:
Geological Survey (U.S.)
Object Type:
Map
System:
The UNT Digital Library
[INS Interface and I-64 Unit Diagrams]
Four diagrams detailing the Litton LTN-76 Inertial Navigation Systems (INS) interface and two diagrams detailing the I-64 Unit created by Applied Geophysics Inc. for a report summarizing tests performed with the LTN-76 designed to fly an airborne geophysical surveys.
Date:
November 1981
Creator:
Applied Geophysics, Inc.
Object Type:
Technical Drawing
System:
The UNT Digital Library
[Camarillo, Beaver, and Bakersfield INS Test Program Maps]
Flight path maps for the Bakersfield, Camarillo, and Beaver INS Test Programs created by the Department of Energy, Grand Junction Operations Office.
Date:
November 1981
Creator:
United States. Department of Energy. Grand Junction Office.
Object Type:
Map
System:
The UNT Digital Library
NPR; Tube to Nozzle Connection and Zircaloy-2 to Stainless Steel Tube Connection
Zircaloy-2 tubing was successfully joined to austenetic and ferritic stainless steel tubing by fusion bonding. Tungsten inert gas welding was employed to join a flange to a pressure tube. This work was performed to help determine the design of pressure tubes of a pressure tube reactor.
Date:
November 18, 1958
Creator:
Smith, W. R. & Klepfer, H. H.
Object Type:
Report
System:
The UNT Digital Library
Removal of Chloride From Congo Precipitates
Uranium precipitates obtained from Congo leach liquors by an ion exchange process contained more than 0.1 percent chloride. Attempts were made to reduce the chloride content of typical precipitates by calcination of dried precipitate, releaching of dried precipitate with water, and washing of wet precipitate with water. Washing of wet precipitate with an aqueous solution of 0.25 percent Na2SO4, to prevent peptization, provided a simple solution to the problem.
Date:
November 3, 1953
Creator:
Viklund, Hans I. & Kennedy, Richard H.
Object Type:
Report
System:
The UNT Digital Library
Calcining-Amenability Testing of Rand Precipitates
Test work on two samples of high-grade Rand uranium precipitate indicated the desirability of calcining it at 400' to 500'C. to cut shipping costs and provide a refinery feed quite amenable to treatment by the nitric acid digestion-TBP process.
Date:
November 26, 1951
Creator:
Bloecher, F. W.
Object Type:
Report
System:
The UNT Digital Library
The Effect of Gallium on Plutonium Assay
Several of the plutonium assay methods were reexamined as part of a continuing effort to make improvements in these frequently used analyses. This investigation included a study of the controlled-potential coulometric, amperometric, potentiometric, and photometric titration methods and their applications to assays of delta-stabilized and alpha plutonium metal.
Date:
November 1962
Creator:
Bergstresser, K. S. (Karl Samuel), 1909-2004 & Waterbury, Glenn R.
Object Type:
Report
System:
The UNT Digital Library
Magnetic Field Distributions in a Pinched Discharge
By use of small magnetic probes inserted into the discharge, the magnetic field distributions in the interior of a high-power pinched discharge have been measured as a function of time. From these data the current distributions can be deduced. By applying a static pressure calculation, in the cases when the radical pinch accelerations are small, the plasma pressure nkT in the pinch has been determined, with superimposed axial magnetic fields, and for stable and unstable configurations.
Date:
November 20, 1956
Creator:
Burkhardt, L. C.; Lovberg, Ralph H. (Ralph Harvey) & Phillips, J. A.
Object Type:
Report
System:
The UNT Digital Library
Critical Masses of Oralloy Lattices Immersed in Water
Certain oralloy (Oy) lattices were immersed in infinite water for determining critical masses at various low-Oy densities. Three Oy unit sizes were used. In a broad sense the experiment shows safe and unsafe conditions for handling heterogeneous Oy-water mixtures.
Date:
November 1955
Creator:
Hoogterp, J. C.
Object Type:
Report
System:
The UNT Digital Library
Analysis of Thorex Pilot Plant Radiation Exposures During 1955
The Thorex Pilot Plant at Oak Ridge National Laboratory was operated during 1955, processing reactor-irradiated thorium slugs to recover U233 and thorium and 12 MTR fuel elements to recover U235 and Np237. The radiation exposure received by operating personnel during this period averaged 60 mrcp/man-week. Most radiation exposure was received in areas that were intended to be only slightly or nonradioactive. However, because insufficient decontamination of process solutions was achieved and equipment surfaces became contaminated from equipment failures, these areas became primary sources of personnel exposure. The installation of additional shielding where needed and the prompt removal of surface contamination successfully reduced the radiation levels and exposures in these areas. Remote control of processing equipment and sampling of very radioactive solutions from process equipment was successfully accomplished, and assisted in the reduction of exposure to operating personnel.
Date:
November 16, 1956
Creator:
McCarley W. T.
Object Type:
Report
System:
The UNT Digital Library
Metallurgy Division Semiannual Progress Report for Period Ending April 10, 1956
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 scholarly output and summaries of general corrosion, dynamic corrosion, mechanical properties, nondestructive testing, welding and brazing, fabrication, physical chemistry of corrosion, HRP metallurgy, the package power reactor program, APPR absorber, metallurgical materials and processing, metallography, ceramics, fundamental physico-metallurgical research.
Date:
November 2, 1956
Creator:
Frye, J. H., Jr.; Manly, W. D. & Cunningham, J. E.
Object Type:
Report
System:
The UNT Digital Library
Electronuclear Research Division Semiannual Progress Report for Period Ending September 20, 1955
The installations of the beam deflector in the ORL 86-inch Cyclotron is sufficiently complete to allow initial testing the system permits the optional use of high-current internal targets. A survey of [illegible] cross sections made with 14-Mev neutrons indicates qualitative agreement with statistical theory. An internal-conversion ion spectrograph and a fission-fragment spectrograph were built and put in operation. The [illegible] functions severed proton-induced reactions of possible use in isotope production were measured. A capsule-type target is being used for the irradiation of chemical compounds. Nuclear physics research with 26-Mev nitrogen lens from the ORNL 63-inch Cyclotron concerned the following: a theoretical interpretation of elastic nitrogen-nitrogen scattering a detailed investigation of some nitrogen-nitrogen nuclear reactions; the measurement of reactions across sections in boron and aluminum; and the identification and the energy spectre of protons and alpha particles resulting from nitrogen-induced reactions with light elements. A study is being made of the practicality of a fixed-frequency cyclotron to accelerate protons to about 1 [illegible] for application in [illegible] research. Phase compensation would be obtained with an unusual magnetic-field configuration which has eight [illegible] cycles with about 72 deg of spiral, Also, a proposal was made to convert the 44-in. proton cyclotron a …
Date:
November 1955
Creator:
Livingston, Robert S. & Howard, F. T.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Results of APPR Critical Experiments, Part I.
This memorandum is the first in a series reporting progress in the program of critical experiments in the ORNLArmy Package Power Reactor Project. The critical assembly, designated as CA-25, is analogous to the APPR design core and consists of 45 fuel boxes, in a 7 x 7 array with the corners removed, contaIned in a large water tank. Two sides of each box are slotted for the insertion and positioning of any desired loading of eighteen plates of fuel, structural material, and poison. The array is submerged in water to provide a moderated and reflector. Enriched uranium metal, in two-mil-thick foils 2.5 x 22 in, is encased in type 304 stainless steel sheets, 2.7 x 23 x 0.0105 in., to form fuel plates. Stainless steel plates, 2.7 x 23 x 0.025 in. are used to simulate additional steel in the APPR core. It is, therefore, possible to maintain an essentially constant metal to water ration in the assembly when the fuel content is varied. The fuel is distributed as uniformly as possible in all boxes and a symmetrical distribution of materials is maintained in the core at all times. Fuel plates containing half-width (1.25 in) uranium foils are provided for …
Date:
November 25, 1955
Creator:
Williams, D. V. P.
Object Type:
Report
System:
The UNT Digital Library
ORNL Mortal Recovery Plant: Processing of ORNL Graphite Reactor Fuel Elements During the Period July and August, 1955
From July 7 to August 31, 1955, 20 tons of uranium and 1,200 g of plutonium were recovered in 47 days of plant operation at an average rate of 833 lb/day of uranium and at a cost of $2.60/lb of uranium. Uranium and plutonium recoveries were, respectively, 99.9 and 95.5 per cent.
Date:
November 11, 1955
Creator:
Brooksbank, R. E.; Chandler, J. M. & Hylton, C. D.
Object Type:
Report
System:
The UNT Digital Library
Determination of Traces of Uranium Metal by Decomposition of the Hydride
Two methods were developed for the determination of uranium metal in UF3 with other fluoride compounds. A simplified method of determination which has a relatively high degree of precision (coefficient of variation 2 per cent) is carried out by decomposing the hydride in an atmosphere of carbon dioxide and subsequently measuring the hydrogen over an aqueous solution of potassium hydroxide. The ignition of the hydride in an atmosphere of oxygen and volumetric measurement of the water at reduced pressures provide a more sensitive method of determination. The coefficient of variation of the latter procedure is 7 per cent. The yield of gas from the reaction of the hydride with ammonia and gaseous hydrogen chloride was found to be neither stoichiometric nor reproducible.
Date:
November 9, 1955
Creator:
Meyer, A. S., Jr.; McDowell, B. L. & White, J. C.
Object Type:
Report
System:
The UNT Digital Library
Determination of Trivalent Uranium with Methylene Blue
A direct titrimetric method for the determination of trivalent uranium in uranium trifluoride and mixtures of fused fluoride salts was developed. The method is based on the stoichiometric oxidation of trivalent uranium to the tetravalent oxidation state with an acidic solution of methylene blue. The sample containing trivalent uranium is dissolved at room temperature in an excess of standard methylene blue solution in a carbon dioxide atmosphere; the excess oxidant is variation of the method is 1.5 per cent for 5 mg quantities of trivalent uranium. The method was applied to various mixtures of fluoride salts containing both trivalent and tetravalent uranium.
Date:
November 22, 1955
Creator:
Ross, W. J.; Meyer, A. S.; White, J. C.; Kelley, N. T. & Susano, C. D.
Object Type:
Report
System:
The UNT Digital Library