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Recovery of Uranium From Fiberglass Air Filters

Description: Abstract: Various procedures for extracting uranium from fiberglass air filters have been tested and compared. Satisfactory results which involve the least amount of handling are obtained by simply washing the material with hot 1:1 hydrochloric acid.
Date: August 5, 1946
Creator: Adams, R. H.; Rogers, J. A. & Brown, K. B.
Partner: UNT Libraries Government Documents Department
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A Study of Efficiencies and Pressure Drop Characteristics of Air-Filtering Media

Description: Removal of particles from air is discussed in terms of three classes of filtering media--air-sampling, respirator, and air-cleaning. Plots of efficiency versus filtering velocity are presented. The pressure drop characteristics of the filters are discussed in terms of initial pressure drops of the clean filters, variations in pressure drop of the individual filters, and comparison of loading rates.
Date: August 10, 1953
Creator: Adley, F. E.; Scott, R. H. & Gill, W. E.
Partner: UNT Libraries Government Documents Department
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Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO

Description: Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects.
Date: August 23, 1956
Creator: Andelin, Robert L.; Anderson, Edward L. & McVey, W. H.
Partner: UNT Libraries Government Documents Department
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U-10 Wt % Mo Fuel Element: Irradiation in SRE

Description: From abstract: The fuel element assembly was successfully irradiated in the SRE to a maximum burnup of 5300 Mwd/MTU, at a peak fission rate of approximately 1.5 x 10E13 fissions/cm3-sec and a maximum central temperature near 1200F.
Date: August 31, 1965
Creator: Arnold, J. L.; Miller, K. J. & Peterson, R. M.
Partner: UNT Libraries Government Documents Department
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LMFR-9 Static Corrosion Behavior of Materials in Bismuth and Uranium-Bismuth Solution at 550°C

Description: Report issued by the Brookhaven National Laboratory discussing corrosion behaviors of materials in bismuth. As stated in the introduction, "this report will present the details of the corrosion testing and the results obtained to date on materials tested under static conditions in bismuth media" (p. 1). This report includes tables, illustrations, and photographs.
Date: August 1954
Creator: Atherton, J. E.; Kammerer, O. F.; Klamut, C. J. & Sadofsky, J.
Partner: UNT Libraries Government Documents Department
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Corrosion Product Activity Distribution Across the Chemical Process System in the Consolidated Edison Thorium Reactor Plant

Description: A study has been performed to determine the corrosion product and water impurity activities in the CETR Chemical Process System. A simplified mathematical model is used to represent the physical situation; however, the magnitude of the activities, taken at the end of the core life to represent the most conservative case, is considered sufficiently accurate for engineering calculations.
Date: August 1960
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: August, 1957

Description: A monthly report summarizing work performed by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. In this monthly report the R&D budget was reviewed, two-dimensional calculations were performed, analysis work was started on control rods and their housing, as well as continued work on the development of the LMFRE reactor.
Date: August 1957
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Uranium Deposits in Southwestern Colorado Plateau

Description: Abstract: The southwestern part of the Colorado Plateau province was studied to test results from experimental simulation of Colorado Plateau type uranium deposits and to search out additional agents influencing uranium precipitation which might be investigated experimentally.
Date: August 1952
Creator: Bain, George W.
Partner: UNT Libraries Government Documents Department
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Irradiation Test Program for the Consolidated Edison Thorium Reactor

Description: The Irradiation Test Program for the Consolidated Edison Thorium Reactor was conducted to obtain confirmation of the stability and performance of the reference fuel element materials and of test assemblies under design operation conditions. The irradiated specimens were tested to determine mechanical properties and corrosion resistance to borated water.
Date: August 1960
Creator: Baker, P. B.; Dzura, E. J. & Johnson, C. R.
Partner: UNT Libraries Government Documents Department
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Approximate Models for Distributed-Parameter Heat-Transfer Systems

Description: Summary: The use of dimensionless-parameter frequency response diagrams to determine accuracies of lumped-parameter approximations is demonstrated by two examples: calculation of the heat flux at the surface of a semi-infinite solid due to temperature fluctuations of an adjacent fluid; and the response of a counterflow heat exchanger to inlet fluid temperature perturbations. Dimensionless system parameters make it possible to use general-purpose plots to find the error in particular approximations as a function of the frequency of perturbation. Such plots are directly applicable to control-system stability problems, where the highest frequency of interest is usually apparent.
Date: August 20, 1963
Creator: Ball, S. J.
Partner: UNT Libraries Government Documents Department
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Diffusion of Stack Gases in Very Stable Atmospheres: Case II

Description: In 1949 Barad presented two solutions to the general diffusion equation. Basic in both solutions is the assumption that in very stable atmospheres a point source may be replaced by a vertical area of uniform concentration at a short distance downwind. This vertical area is considered to exist at the distance at which the plume finally "levels-off" and assumes a flat ribbon-like appearance. In addition if the distance over which diffusion takes place is limited to one or two miles and if only the stable atmosphere with its narrow range of eddy sizes is considered, the average diffusion co-efficient (K) has a signficance which it does not have in the case of neutral equilibrium.
Date: August 10, 1953
Creator: Barad, M. L. & Shorr, B.
Partner: UNT Libraries Government Documents Department
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Phenix City 1° x 2° NTMS area, Alabama and Georgia: data report (abbreviated)

Description: From Introduction: "The data presented here are reconnaissance data intended for use in identifying broad areas for further study. While care has been taken to provide reliable sampling and analyses, verification of individual analyses is beyond the scope of this report. The data should be viewed statistically because "one-point anomalies" may be misleading. Regional trends, however, should be reliable."
Date: August 1981
Creator: Bennett, C. B.
Partner: UNT Libraries Government Documents Department
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San Bernardino 1° x 2° NTMS Area, California: Data Report (Abbreviated)

Description: From abstract: This abbreviated data report presents results of ground water and stream/surface sediment reconnaissance in the National Topographic Map Series (NTMS) San Bernardino 10 x 2 quadrangle. Surface sediment samples were collected at 1539 sites, at a target sampling density of one site per 13 square kilometers (five square miles). Surface water samples were collected at 39 of these sites. Ground water samples were collected at 392 sites. Neutron activation analysis (NAA) results are given for uranium and 16 other elements in sediments, and for uranium and 9 other elements in ground water. Mass spectrometry results are given for helium in ground water. Field measurements and observations are reported for each site. Analytical data and field measurements are presented in tables and maps.
Date: August 1981
Creator: Bennett, C. B.
Partner: UNT Libraries Government Documents Department
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The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings

Description: Report containing a series of drawings detailing the Oak Ridge National Laboratory's high flux isotope reactor, its surroundings, and its systems.
Date: August 1964
Creator: Binford, F. T.; Cramer, E. N. & Cramer, E. N.
Partner: UNT Libraries Government Documents Department
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The Photoproduction of Mesons from Hydrogen

Description: In an effort to gain information on the nature of the photon-meson and photon-nucleon interaction, a study of the artificial production of mesons by photons has been made at the Berkeley synchrotron. The major effort of this research was concentrated on a measurement of the energy and angular distribution of u+-mesons produced when the photons strike a target of liquid hydrogen. Detection of the mesons is accomplished electronically by the technique of delayed coincidence.
Date: August 24, 1950
Creator: Bishop, Amasa Stone
Partner: UNT Libraries Government Documents Department
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Dissolution of Power Reactor Fuel Cores

Description: Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials.
Date: August 26, 1960
Creator: Blaine, H. T.
Partner: UNT Libraries Government Documents Department
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