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Aging Characteristics of Hastelloy B

Description: Report issued by the Oak Ridge National Laboratory discussing the aging characteristics of the alloy Hastelloy B. Materials, equipment, experimental procedures, and results used to determine the characteristics of the alloy are presented. This report includes tables, illustrations, and photographs.
Date: August 12, 1957
Creator: Clausing, Robert E.; Patriarca, P. & Manly, W. D.
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 June 10, 1952

Description: This quarterly progress report details ongoing work at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. Topics of discussion include reactor theory and design, shielding research, materials research, appendixes with information on ongoing analytical chemical studies.
Date: August 5, 1952
Creator: Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, W. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of the Combustion of Graphite-Uranium Fuels in a Fixed Bed or Moving Bed

Description: The first step in a proposed processing method for recovery of uranium from graphite-uranium fuels consists of oxidation of the fuel by oxygen to volatilize the carbon. Residue ash from the combustion step can be treated in a variety of ways to recover and purify the uranium. The combustion step may be caried out by contacting the solid fuel in a fixed or moving bed with a stream of oxygen-bearing gas in a tubular or annular reactor. Oxidizing gas may be introduced to the reactor at several poi… more
Date: August 13, 1964
Creator: Scott, Charles D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Applied Health Physics Annual Report for 1963

Description: Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs.
Date: August 1964
Creator: Morgan, K. Z.; Davis, D. M.; Hart, J. C.; Abee, H. H.; Gupton, E. D. & Warden, A. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Attempt to Duplicate a Direct Spectrophotometric Method for Thorium Proposed by Gurupada Bannerjee

Description: An attempt was made to apply a method developed by G. Bannerjee to the colorimetric determination of thorium. In this method, 2-p-sulfophenylazo-1, 8-dihydroxynaphthalane-3, 6-disulfonic acid (SPAINS) is used as the chromogenic reagent. Thus far, Bannerjee's results have not been reproduced in this work.
Date: August 13, 1959
Creator: Holsopple, H. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation of Effective Resonance Integrals

Description: Effective resonance integrals for fuel and fertile materials were calculated as a function of materials concentration in homogeneous media. For the fissile materials (U-235, Pu-239), results were obtained from multigroup, monte-carlo, and statistical model calculations. For the fertile materials (U-238), results were obtained from monte-carlo and multigroup calculations and were compared with experimental results.
Date: August 28, 1959
Creator: Jaye, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation of Radial Neutron-Flux Distribution in EGCR Lattice Cell

Description: The Neutron-flux distributions in an EGCR cell containing seven rod clusters of 2.0 and 2.6% enriched uranium oxide have been obtained by using a one-velocity, one-dimensional P-3 solution to the neutron-transport equation and adjusting fluxes in the fuel cluster in a manner which is consistent with previous comparisons of experimental and calculated distributions. Flux traverses in the outer rod perpendicular to a diameter of the cluster are also presented.
Date: August 31, 1959
Creator: DeBoer, T. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation of Transport Cross Sections

Description: Many elements exhibit anisotropic scattering at energies of interest in reactor calculations. A method is presented for the calculation of transport cross sections including the observed anisotropy.
Date: August 5, 1959
Creator: Nestor, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Californium Production in the High Flux Isotope Reactor

Description: Californium-252 and other isotope production rates resulting from irradiating Pu-242 in the proposed High Flux Isotope Reactor were estimated. The effect of curium recycle was investigated and optimum irradiation cycles determined.
Date: August 31, 1959
Creator: Claiborne, H. C. & Lietzke, Marjorie P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Development Section C Monthly Progress Report July 1959

Description: Nitrate contained in raffinates from Canadian Blind River mills interferes seriously with thorium extraction by secondary amines. With primary amines, however, the effect is negligible and these compounds are the preferred process extractants.
Date: August 5, 1959
Creator: Brown, K. B.; Allen, K. A.; Blake, C. A.; Coleman, C. F.; Crouse, D. J.; Ryon, A. D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparison of the Thermal Conductivity, Electrical Resistivity, and Seebeck Coefficient of a Hight-Purity Iron and Armco Iron to 1000 [degrees] C

Description: The thermophysical properties of Armco iron such as thermal conductivity, electrical resistivity, and Seebeck coefficient have been extensively investigated and reviewed up to 1000 degrees C. Few investigations of such properties have been made on high purity iron. If such a study is made using the same apparatus to determine the properties of two purity levels of iron, then several significant intercomparisons can be made which add meaning to data on a single material. The systemic errors for … more
Date: August 11, 1964
Creator: Moore, J. P.; Fulkerson, W. & McElroy, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Compound CuO-3UO3

Description: A double oxide of uranium and copper has been found to exist at 300'C in the four-component system UO3-CuO-SO3-H2O. This new compound is shown to be CuO-3UO3. The method of preparation, analyses, and characterization of the compound are given. Some comments are made with regard to the homogeneous reactor fuel solution.
Date: August 25, 1959
Creator: Gill, J. S. & Marshall, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables

Description: Report presenting the calculation of the costs incurred in shipping irradiated uranium-containing fuel elements. A computer code that designs a cask and calculates the shipping costs is presented. By use of the code, shipping costs were calculated for typical reactor fuels.
Date: August 1964
Creator: Salmon, Royes
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Core Levitation in the EOCR in Case of Main Coolant Pipe Failure

Description: This memorandum summarizes the results of an analysis to determine the extent of displacement of the EOCR core due to blowdown in case of several postulated hot main gas coolant pipe failures. Results show that the core will be damaged for any hot pipe double-ended failure. Excepting the improbable case of no coolant flow existing proper to the break, the core will be damaged for any hot pipe fracture exposing a total flow area to the atmosphere equal to that of one pipe. Smaller breaks will pr… more
Date: August 4, 1959
Creator: Fontana, M. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Demonstration of the Zirflex Process on Irradiated PWR Blanket Fuel

Description: Fifteen PWR blanket fuel specimens, varying in burnup from 80 to 1100 Mwd/T, were declad with boiling 6 M NH4F-1.0 M NH4NO3 before the UO2 core was dissolved in 10 M HNO3-uranium and plutonium losses to the decladding solution were less than 0.2% in nearly all runs.
Date: August 24, 1959
Creator: Gens, T. A.; West, G. A. & Ferris, L. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Deposition of Submicron-Size Particles in Ventilation Ducts

Description: The purpose of this study was to investigate mathematically the concentration decrease due to particle deposition phenomena in highly concentrated monodispersed aerosols (mean particle size less than 1.0 mu) flowing through ventilation ducts. It was found that, from the standpoint of removal, the decrease in concentration due to deposition on duct walls was insignificant; but, when considering contamination on duct walls, the amount deposited, even though small when compared with the amount in … more
Date: August 1964
Creator: Davis, L. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Suitable Insulation for a 1-5/16" Helium Filled Annulus in the ORR Helium In-Pile Loop, Design No. 4

Description: Heat loss tests were conducted with six insulation configurations for application in the riser regenerator and auxiliary regenerator sections of the loop. Insulation consisting of ten laminations of 0.003 in. stainless steel shim stock spaced 1/8 inch apart produced a temperature drop across the 15/16 inch annulus of 1200 F with a heat loss of 1.04 KW per foot of 2 inch schedule 40 pipe. The curve of heat loss vs. temperature difference is presented which, with results of similar tests with a 1… more
Date: August 17, 1959
Creator: Knight, R. B. & Helms, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Equilibrium Calculation in the System: Uranyl Nitrate, Nitric Acid, Water, TRP, and Kerosene Diluent Using the ORACLE Digital Computer

Description: A set of equations was written which allowed the calculation of equilibrium concentrations in the solvent phase of nitric acid and uranyl nitrate, given the initial TRP concentration in the solvent and the aqueous phase concentrations of acid and uranium. An ORACLE subroutine was written based on these occasions which will calculate a set of equilibrium values in about 35 milliseconds.
Date: August 12, 1959
Creator: Jury, S. H. & Whatley, M. E. (Marvin E.), 1926-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Flame Photometyry for the Determination of Elements of the Rare-Earth Group

Description: Flame spectra are presented of all rare-earth elements except cerium and promethium, and also of the closely related elements, scandium and yttrium. The precise wave length and relative spectral intensity of each line and band, as well as the band width of all bands, are tabulated. Also included in this tabulation are the relative spectral interferences of other elements of the group studied which interfere with the emissivity measurements of the bands and lines listed. Based on the spectra and… more
Date: August 27, 1959
Creator: Menis, Oscar, 1913-1979
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Feasibility Report on a Method of Direct Total Body Measurement of Enriched Uranium in Man

Description: In certain phases uranium processing it is poss!ble for operating personnel to acquire internal deposits of uranium. This body burden can be acquired by injection, as in contamination of a wound, by ingestion, of by inhalation. In order to estimate internal exposures, some means of determining the location and extent of these internal deposits is essential.
Date: August 7, 1959
Creator: Sanders, Fred W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Further Evaluation of Check Valve Material For The Homogeneous Reactor Program

Description: A number of materials were tested to improve check valve trim material selection for aqueous homogeneous system fluids. Previous recommendations of Stellite 3 and 17-4 PH stainless steel were found valid for uranyl sulfate and distilled water service, respectively. Aluminum oxide and boron carbide were found applicable to ThO2 slurry service. Test runs demonstrate that check valve hardware is now available to pump slurry for at least 3 months of continuous duty.
Date: August 4, 1959
Creator: Blumberg, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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