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COMPARATIVE COST STUDY OF PROCESSING STAINLESS STEEL-JACKETED UO$sub 2$ FUEL: MECHANICAL SHEAR-LEACH VS SULFEX-CORE DISSOLUTION

Description: The economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO/sub 2/ nuclear fuels were compared. A 2.66 metric ton U/day head end portion of a plant was designed for each process and capital and operating costs were developed. For plants of this size and larger, mechanical shear-leach processing has the advantage of ~20% lower capital cost and 50% lower operating cost. Processing costs of… more
Date: April 23, 1962
Creator: Adams, J. B.; Benis, A. M. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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Neutron Dosimetry in and Around Human Phantoms By Use of Nuclear Track Emulsion

Description: The validity of the nuclear track emulsion technique for fast-neutron dosimetry is examined in the exposure of a human phantom to PuBe neutrons, Semiautomatic track scanning and high-speed data analysis obviate the major disadvantages of emulsion dosimetry, and allow the absolute differential proton track energy spectrum at various locations in the phantom to be obtained without a serious cost in time. From this are calculated the total absorbed local tissue dose due to proton recoils and the l… more
Date: April 1962
Creator: Akagi, Hiroaki & Lehman, Richard L.
Partner: UNT Libraries Government Documents Department
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SODIUM MASS TRANSFER: III. THE APPLICATION OF LIQUID AMMONIA AS A SODIUM LEACHING AGENT

Description: A technique is presented for liquid ammonla leaching of metallic sodium from corrosion coupons, filter elements, and sodium samples to reveal contaminants and impurities. The advantages of the method in preserving the physical form of corrosion or mass-transfer deposits are demonstrated. A possible application to the determination of trace oxygen in sodium is mentioned. (auth)
Date: April 1962
Creator: Alter, H.W. & McManus, P.A.
Partner: UNT Libraries Government Documents Department
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C reactor overbore fuel failures

Description: The concept of overboring the graphite channels in an older Hanford reactor and installing oversized tubes charged with oversize fuel elements is being investigated at C reactor. Recently a column of these oversized test fuel elements exhibited three uranium cleavage (split) type failures after experiencing severe reactor flux cycling. This report presents a preliminary description of both the fuel failures and the flux cycling encountered by the reactor.
Date: April 30, 1962
Creator: Ambrose, T. W. & Graves, S. M.
Partner: UNT Libraries Government Documents Department
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Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions

Description: Abstract: The MSAR corrosion test loop was used to study the effect of VKE-shaped crevices on the corrosion resistance of Zircaloy under boiling heat-transfer condtions in both ammoniated and lithiated water at pH 10.5.
Date: April 1962
Creator: Anderson, W. Kermit & McGoff, M. J.
Partner: UNT Libraries Government Documents Department
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The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium

Description: The adsorption of ethane, ethylene, and acetylene on clean iridium in a field emission microscope was found to cause characteristic changes in the work function of the iridium surface. Further changes, which were time and temperature dependent, resulted when such surfaces were heated. Flash filament experiments showed that the changes in work function upon henting are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a linear relationship be… more
Date: April 1, 1962
Creator: Arthur, J. R., Jr. & Hanson, R. S.
Partner: UNT Libraries Government Documents Department
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The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium

Description: From abstract: "The adsorption of ethane, ethylene and acetylene on clean iridium in a field emission microscope has been found to cause characteristic changes in the work function of the iridium surface. Further changes, which are time and temperature dependent, result when such surfaces are heated. Flash filament experiments have shown that the changes in work function upon heating are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a li… more
Date: April 7, 1962
Creator: Arthur, John R., Jr. & Hansen, Robert S.
Partner: UNT Libraries Government Documents Department
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Effect of 1200ºF Sodium on Austenitic and Ferritic Steels Progress Report: March 1962

Description: This is the nineteenth progress report regarding progress made in testing several Cr-Mo and stainless steel specimens and including photomicrographs in the report, fatigue, creep, and stress in sodium test results, and creep, stress, and tensile in air and helium test results.
Date: April 18, 1962
Creator: Barker, K. R.; King, E. C.; Andrews, R. C. & Werner, R. C.
Partner: UNT Libraries Government Documents Department
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An Investigation of the Corrosion Resistance of Brazing Alloys for Austenitic Stainless Steel Fuel Elements for Service in 565 F Pressurized Water

Description: Since brazing was the method selected for joining the stainless steel SM- l reactor fuel element, corrosion studies were conducted on various potential brazing alloys to evaluate their resistance under the approximate pressurized- water conditions of the SM-1. The program consisted mainly of testing type 304L stainless steel T'' joints brazed with selected alloys in quiescent, degassed, and deionized autoclaved water at 565 deg F under 1200-psi pressure. In the initial phase of the investigatio… more
Date: April 12, 1962
Creator: Beaver, R. J.; Leitten, C. F. Jr. & English, J. L.
Partner: UNT Libraries Government Documents Department
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A PINHOLE CAMERA AUTORADIOGRAPHIC TECHNIQUE FOR ENCAPSULATED IRRADIATED FUEL SPECIMENS

Description: A gamma pinhole camera was devised to permit a nondestructive examination of irradiated specimens while still in sealed capsules. The camera was designed such that a complete experiment may be withdrawn from an irradiation facility, the specimen autoradiographed, and the experiment then reinserted if so desired. The pinhole aperture is 0.020 in., and the source to pinhole block is 4 ft. The image-to-source sizes are a one-to-one ratio. The resolution of the image is 0.03 in. (auth)
Date: April 1, 1962
Creator: Beck, W.N.
Partner: UNT Libraries Government Documents Department
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Sherwood Progress Report No. 5, January 1961-December 1961

Description: "This report is a summary of activities related to Project Sherwood at the Magneto-Fluidd Dynamics Division of the Courant Institute of Mathematical Sciences of New York University from January 1961 to December 1961. Substantial investigations are summarized under the following subject headings: Charged Particle Trajectories, Cusped Geometries, Collisionless Shock Theory, Wave Propagation, and other subjects."
Date: April 16, 1962
Creator: Berkowitz, J.
Partner: UNT Libraries Government Documents Department
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Neutron Thermalization Measurements Using an Electron Linear Accelerator

Description: Discussions are presented concerning integral experiments primarily on water and graphite systems. A description of experimental facilities is included along with details of die-away experiments, infinite-medium spectrum measurements, spatially dependent spectrum measurements, spectrum measurements for graphite systems, and development of a subcritical assembly program. (J.R.D.)
Date: April 10, 1962
Creator: Beyster, J. R.
Partner: UNT Libraries Government Documents Department
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Air flow inspection of Rover fuel elements

Description: This report addresses two inspection systems that have been constructed which use strain gage pressure transducers to pick up changes in static pressure due to change in the hole diameter.
Date: April 11, 1962
Creator: Blanks, J. R. & Wright, C. C.
Partner: UNT Libraries Government Documents Department
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A STUDY OF THE SHIELD OF THE UNIVERSITY OF ILLINOIS TRIGA MARK II RESEARCH REACTOR

Description: Detailed measurements were made of the fast-neutron and gamma dose rates and the thermal-neutron fluxes existing at the surfaces of the biological shield of the University of Illinois TRIGA Mark II Research Reactor. Dose rates and fluxes were found to be extremely low. A comparison was made by means of threshold foil techniques between the fast-neutron flux in a beam hole of the reactor during steady-state operation at 1 kw and during a nominal 250 Mw, 30 msec pulse produced by rapid insertion … more
Date: April 23, 1962
Creator: Blosser, T.V.; Freestone, R.M. Jr. & Miller, J.M.
Partner: UNT Libraries Government Documents Department
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NPR Physics Startup Testing Program

Description: The New Production Reactor, as compared to existing Hanford reactors, employs new and unique design concepts. To properly evaluate these design concepts and their effects on reactor operations, nuclear safety, and reactor life, a comprehensive testing program is planned; this program, with its objectives and restrictions, is discussed in this report. It has been developed along the same line as the C and K Reactors test, programs, and is expected to require a total time of 6--8 weeks of round-t… more
Date: April 25, 1962
Creator: Bowers, C. E.
Partner: UNT Libraries Government Documents Department
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Equation of State of Classical Systems of Charged Particles

Description: Recent developments in the classical theory of fully ionized gases and strong electrolyte solutions are reviewed, and are used to discuss the equation of state at high temperature and low densities. The pressure is calculated using the ring-integral approximation, and quantitative estimates of higher correction terms are given. The effect of short-range repulsive forces is shown by comparing the results with two kinds of potential functions: hard spheres of diameter a, and "soft" spheres for wh… more
Date: April 26, 1962
Creator: Brush, S. G.; DeWitt, H. E. & Trulio, J. G.
Partner: UNT Libraries Government Documents Department
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Measurement of Xenon Poisoning in the HRT

Description: Measurements obtained during three periods of HRT operations indicated that the xenon poison fraction was approximately 0.010. The technique used was based on mass spectrographic analyses of the stable xenon isotopes in the reactor off-gas stream. Models proposed to explain the measurements show that xenon, which is formed primarily by decay of iodine adsorbed on the pipe walls, is held up on the walls, out of the circulating stream, for an average period of about eight hours. (auth)
Date: April 19, 1962
Creator: Burch, W.D.
Partner: UNT Libraries Government Documents Department
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