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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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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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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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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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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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Survey of Anodizing Processes for Aluminum

Description: A preliminary survey of the literature concerning anodizing and oxide treatments for aluminum was made for the purpose of selecting a method for anodization which would produce, on aluminum, a 0.2-mil oxide film of high density with reasonable durability and abrasive resistance and which would have high electrical insulating characteristics. A summary of this survey and recommendation are given in this report.
Date: August 27, 1959
Creator: Holsopple, H. L.
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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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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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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Spectrographic Analysis of Normal Human Tissue From Richmond, Virginia

Description: As a part of the Internal Dose Program, normal human tissues are analyzed spectrographically for approximately 40 minor and trace elements. This study is performed by the Health Physics Division and the Physics Department, University of Tennessee, under Subcontract 380. Because the amount of data is large, central files reports have been issued which include the data on all tissues received from a city. This is the sixth report in the series, and all tissues here reported upon were received fro… more
Date: August 25, 1959
Creator: Tipton, I. H.; Cook, M. J.; Foland, J. M.; Rittner, Johanna; Hardwick, Michael & McDaniel, K. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

In-Line Gamma Monitoring

Description: Two cell designs for in-line gamma monitoring have been tested as part of the Power Reactor Fuel Reprocessing Program. The fluorothene tube cell has operated for six months in the 3019 Pilot Plant Building. The success and acceptance of this instrument as a process monitor has been attributed to its fast response, reliability of the measurements, and the ease of operation and maintenance. Operation of a falling stream cell in the 3505 Building Metal Recovery Plant demonstrated the need for furt… more
Date: August 26, 1959
Creator: Mackey, T. S. (Tom S.)
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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Testing of Dump Valve Trim in the Valve Test Loop and the Performance of Dump Valves in the HRT

Description: The Homogeneous Reactor Test requires an emergency valve for rapidly releasing the contents of each the core and blanket high-pressure system to its low-pressure system. This report describes the testing of dump valve trim in the Valve Test Loop and the performance of dump valves in the HRT to date.
Date: August 3, 1959
Creator: Hise, E. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Methods for Applying Transmission and n-vs-E Corrections in the Determination of n2200 by the Macklin-deSaussure Experiment

Description: A careful determination of n2200 from results of the Macklin-deSaussure manganese bath experiment involves corrections for (1) the weak but non-zero transmission of sub-cadmium neutrons through the uranium or plutonium foils, and (2) the small variation of n with energy in the sub-cadmium region. This report presents the derivation of a single general expression for applying both these corrections, and then describes two IBM 704 codes (MTC and GTC) which were written especially to facilitate th… more
Date: August 17, 1959
Creator: Halbert, Edith C.; Maskewitz, Betty F. & Wynn, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Welded Seal-Ring Vacuum Closures

Description: This is a preliminary report dealing with the development of bakeable high-vacuum flanges for the ORNL PIG Facility. A number of flange designs are discussed together with fabrication, inspection, testing, and installation and maintenance information.
Date: August 21, 1959
Creator: Michelson, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Phase Stability of Homogenous Reactor Hot Fuel Solutions

Description: Portions of two samples of HRT fuel solutions were sealed in silica capillary tubes approximately three weeks after they were removed from the reactor and the temperature at which each solution separated into two liquid layers was determined.This report gives the results of these observations.
Date: August 18, 1959
Creator: Barton, C. J.; Gill, J. S.; Hebert, G. M.; Marshall, W. L. & Moore, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reprocessing of ARE Fuel, Volatility Pilot Plant Runs E-3 Through E-6

Description: The Fluoride Volatility Process was developed to recover uranium from fused salt reactor fuels. After two testing runs had been completed processing was interrupted because of a UF6 leak. After all faulty connections and seals had been made gas-tight, processing of the ARE fuel was resumed and carried to completion. This report covers processing of the ARE fuel through the last four runs plus a summary of the entire ARE reprocessing program.
Date: August 26, 1959
Creator: Whitmarsh, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurement of the "Active Deposit" of Thoron

Description: A description is given of the properties of the nuclides included in the "active deposit" of thoron. A method is presented for obtaining a quantitative measurement of the activity of the transient-equilibrium mixture.
Date: August 17, 1959
Creator: Reynolds, S. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Surface-Exchange Method for Determination of Surface Area of UO2 Powder

Description: Applicability of the surface-exchange method of determination of surface area of UO2 powder has been investigated. Preliminary results indicate that the method offers a rapid and easy determination of surface area with a precision of ~ 10%.
Date: August 6, 1959
Creator: Ferguson, R. L. & Leddicotte, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Shut-Down Cooling of ORR

Description: The purpose of this memo is to present information which may be used in estimating the magnitude of the shut-down cooling problem in the ORR at various power levels. Using previously estimated data for the MTR (IDO-16443), a rough estimate of the space distribution of heat release after shut-down is presented.
Date: August 14, 1959
Creator: Cole, T. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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