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An Evaluation of the Substitution of Zircaloy for Stainless Steel in n.s. Savannah Fuel-Element Containers. Summary Report

Description: The possibility of reducing fuel-cycle costs for the N.S. SAVANNAH by replacing the stainless steel fuelelement containers in the permanent reactor core structure by similar containers of a zirconium alloy was investigated. These containers, although not integral parts of the fuel-bearing components, are located within the active core and divide the core into 32 separate channels into which the fuel elements are placed. Areas of investigation included reactor physics, fuel-cycle economics, mate… more
Date: November 1, 1963
Creator: Anderson, T. D.; Gross, E. E.; McCurdy, H. C.; Schaffer, L. D.; Shobe, L. R. & Whitmarsh, C. L.
Partner: UNT Libraries Government Documents Department
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Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: November 30, 1963
Creator: Auleta, J. J.
Partner: UNT Libraries Government Documents Department
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Energy Deposition by Fast Neutrons. [Part] II, Yield of the Fricke Dosimeter at 14.6 Mev

Description: A measurement of the yield of the aerated, ferrous sulfate-sulfuric acid (Fricke) dosimeter for 14.6-Mev neutrons gave a value of GF /sub Fe/sup +5/= 11.5 plus or minus 1.8. G/sub Fe/ number of ferric ions produced per 100 ev deposited. The determination combined an analysis of the energy deposit by scattering and charged particle reactions with a determination of the neutron flux by two independent means: (1) a "long counter" method and (2) an activation technique. The result is in reasonable … more
Date: November 1963
Creator: Axtmann, Robert C. & Licari, Joseph A.
Partner: UNT Libraries Government Documents Department
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Nuclear Analysis of PM Long Life Core 3

Description: Introduction. Under AEC contract the Martin Company has followed up the design and construction of the PM-1 and PM-3A nuclear power plants with R&D efforts seeking improved plant efficiency, increased core life and higher operating power. The Advanced PM cores have evolved step by step, with the addition of degrees of freedom to design latitude. A first replacement core, Core 2, has been designed to achieve 50 percent greater life than PM-1 through relatively minor design changes. Core 3 re… more
Date: November 1963
Creator: Bagley, Raymond. & George, Critz.
Partner: UNT Libraries Government Documents Department
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The Crosscorrelation Method of Measuring System Dynamic Response

Description: The basic relations of the crosscorrelation method are presented; and variations of the method for dealing with practical cases for which the idealized relations are inaccurate due to finite experiment length, finite bandwidth of the input signal, and uncorrelated noise in the system response signal are discussed and demonstrated. (D.C.W.)
Date: November 1, 1963
Creator: Balcomb, J. D.
Partner: UNT Libraries Government Documents Department
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Fabrication process test evaluation: Shipping, HI-74-SL

Description: The test parts were canned on October 7, 1962 and October 8, 1963. Only six parts, all radiographic rejects, were used for the test instead of 12 parts as originally planned. The original test called for using one very porous and one relatively non-porous sand cast aluminum insert in each container. Shipping experience has shown no significant effect of porosity of inserts on corrosion severity of parts shipped in them. All inserts used were full contour support inserts. Each test part was cann… more
Date: November 8, 1963
Creator: Barber, A. E.
Partner: UNT Libraries Government Documents Department
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Effect of Eddy Diffusion on Temperatures in a Fixed Bed, Particulate-Fueled Nuclear Reactor

Description: Abstract: To assess diffusion's importance, the temperature distribution in a cylindrical reactor is derived for a coolant with uniform properties and velocity, taking into account both radial and axial diffusion, for a cosine-J0 power distribution. The fractional temperature rise of the coolant is found to be [chemical formula] where E(z) = [sin(z) + sin(Z)]/2 sin(Z), z= π x/2′, x is the axial distance from the core center, -H and ′ are the core half-height and extrapolated half-height, -H≤x≤… more
Date: November 1963
Creator: Barker, James J. & Benenati, Robert F.
Partner: UNT Libraries Government Documents Department
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Lens Opacification in Mice Exposed to Monoenergetic Fast Neutrons

Description: Early effects obtained with monoenergetic fast neutrons in mice have been described elsewhere. Emphasis in this report will be placed on the late effects of lens opacification (cataractogenesis), particularly during the period soon after irradiation with low or fractionated doses of neutrons at two energy levels, or X-rays. Considerations will also be given to the influence of age at time of irradiation upon the induction of lens opacities. Both studies are continuing, with periodic slit-lamp m… more
Date: November 19, 1963
Creator: Bateman, J. L.; Bond, V. P. & Rossi, H. H.
Partner: UNT Libraries Government Documents Department
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Effect of Fluoride Ions on the Aqueous Corrosion of Zirconium Alloys

Description: Abstract. A review has been made of the effects of fluoride ions on the corrosion behavior of zirconium alloys in high-temperature water. Corrosion was found to occur as the result of contamination of the water or the zirconium surface. A major source of fluorides is undue delay in rinsing the HF-HNO3 pickling solution during surface preparation. The oxide on corrosion-resistant material has been found to contain up to 7600 ppm fluoride from this source. The threshold concentration of fluoride … more
Date: November 1963
Creator: Berry, Warren E., 1922-
Partner: UNT Libraries Government Documents Department
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Development status and incentives for the hot die sizing process

Description: The development status and incentives for the hot the sizing process for reactor production fuels is reviewed and updated and economic justification for the process for four different case studies presented. Based on whether the end bonding step can be eliminated, payout periods of 1.2 to 1.7 years can be realized if the present AlSi process (two-shift, five-day week) is converted to hot die sizing for all reactors. For K-Reactor operation only, Payouts of 1.5 to 2.2 years can be realized by co… more
Date: November 20, 1963
Creator: Blanton, W. A.
Partner: UNT Libraries Government Documents Department
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Feasibility of a Liquid Phase Chemonuclear Ozone Process

Description: At the Chemonuclear Workshop held at Brookhaven National laboratory in November 1962 it was pointed out that the production of ozone from oxygen by a liquid phase fission fragment chemonuclear process appears to have reasonable economic potential. The maximum theoretical reaction yield for the formation of ozone from oxygen is a "G" value of 68 molecules for 100 ev based on heat of reaction data. The authors felt a "G" value of 15 to be reasonable for this study. the reactor system chosen has l… more
Date: November 19, 1963
Creator: Cagnetta, J. P.; Goellner, D. & Steinberg, M.
Partner: UNT Libraries Government Documents Department
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Atom to Adam

Description: This report talks about the molecules which constitute today's living organisms
Date: November 1, 1963
Creator: Calvin, Melvin & Calvin, G. J.
Partner: UNT Libraries Government Documents Department
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Development of Fueled Graphite Containing Pyrolytic-Carbon Coated Carbide Particles for Nonpurged, Gas-Cooled Reactor Systems

Description: Abstract: Progress is reported in several areas of development of fueled graphite containing coated particles for nonurged gas-cooled reactor systems. The sol-gel process has been modified for making spherical particles of both thorium-uranium carbide and thorium-uranium oxide suitable for coating. Equipment has been assembled and methods have been developed for deposition of pyrolytic-carbon coating under well-controlled conditions. Damage to coated particles during fabrication into a graphi… more
Date: November 1963
Creator: Carlsen, F. L., Jr.; Bomar, E. S. & Harms, W. O.
Partner: UNT Libraries Government Documents Department
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Analysis of E-N target conversion data

Description: Production efficiency studies of the E-N loading require that conversion ratio values for both plutonium and tritium be defined. Changing of the core-loading charge makeup with each core load to obtain a more efficient loading has theoretically resulted in increasing the tritium conversion ratio. Tritium recovery data from the third H Reactor E-N loading has recently become available for analysis. The buildup of product is much slower in fringe blanket material then in core target pieces. The s… more
Date: November 21, 1963
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
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