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100-B Area flow analysis

Description: Results of experimental programs indicate that it might be desirable in the future to modify the existing reactors by replacing the aluminum process tubes with tubes made of a zirconium alloy. The zirconium tubes would be more corrosion resistant than the aluminum ones and would also be stronger at higher temperatures. These new tubes would have the same outer diameter as the present tubes (for ease of handling and in order to provide adequate graphite cooling) but would have a thinner wall (si… more
Date: June 1, 1957
Creator: Bainard, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Stresses and Deflections in Top Support Grid, PWR Reactor. Final Report

Description: The top grid of the PWR reactor core assembly is treated as a simply supported circular plate. The theory of plate is applied to the grid umder mechanical loads. The thermal stress problem is analyzed by treating the plate as under combined action of a laterally distributed load and forces in the middle plane of the plate. The load distribution is calculated from the temperature variation over the grid. The thermal stress problem then is equivalent to two problems: one, of bendimg of plate; and… more
Date: June 1, 1957
Creator: Yen, T. C. & Vining, R. E., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Carbide Coatings on Graphite

Description: A method has been developed for the uniform coating of graphite tubes with carbides of niobium, tantalum, and zirconinm by thermal decomposition of their respective halide vapors. Conditions of coating temperature and pressure are so chosen as to prevent the deposition of metal, but to permit the formation of the carbide as rapidly as carbon can diffuse to the surface. If the carbon diffusion can be made the rate-limiting step, the coating process becomes self- regulating and uniform thickness … more
Date: June 28, 1957
Creator: Blocher, J.M. Jr.; Ish, C.J.; Leiter, D.P.; Plock, L.F. & Campbell, I.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CHARACTERISTICS OF THE SOLID STATE TRANSFORMATIONS IN-URANIUM

Description: The purpose of the investigation was to determine the temperature dependence of the lattice parameters of U from room temperature to the melting point and to provide experimental data on the general characteristics and kinetics of the allotropic transformations in U. Toward this end high-temperature x-ray diffraction, electrical resistance, and sonic experimental techniques were employed. The data presented are interpreted in terms of the known physical, mechanical, and structural properties of… more
Date: June 1, 1957
Creator: Klepfer, H.H. & Chiotti, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, May 1957

Description: The May, 1957 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation.(MB)
Date: June 21, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Continuous dissolution of uranium fuel elements in a tower dissolver

Description: A continuous process for the dissolution of irradiated fuel elements is a potential means of solving criticality limitations in the dissolution of enriched uranium slugs and of achieving higher dissolver capacity in the Redox and Purex Plants. This report summarizes development studies aimed at determination of dissolution rates, effluent compositions, and effects of changes in operating conditions on mercury-catalyzed dissolution in a tower-type unit.
Date: June 18, 1957
Creator: Evans, T. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF A BATCH PROCESS FOR THE PRODUCTION OF A ZrO$sub 2$-UO$sub 2$ SOLID SOLUTION

Description: A batch process on the 2 kg scale was developed for the production of ZrO/sub 2/--UO/sub 2/ solid solution in the weight proportion of about 4 to 1. The product is tetragonal ZrO/sub 2/-- UO/sub 2/ solution, with no UO/sub 2/ lines showing on the x-ray powder diffraction patterns. The solid solution is prepared from a precipitate of Zr(OH)/sub 4/-- (NH/sub 4/)/sub 2/U /sub 2O/sub 7/ which is filtered, dried, milled, screened to minus 325 mesh, and heated at 9OO deg C in H/sub 2/ for 4 hours. Th… more
Date: June 1, 1957
Creator: Hayter, S. W.; Bard, R. J.; Smith, R. E.; Dumrose, A. C.; Baxman, H. R.; Bertino, J. P. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Disposal of Power Reactor Waste Into Deep Wells

Description: Disposal of wastes from the processing of solid fuel elements and from solid blanket elements is discussed. The subjects considered include extraction of uranium by several methods, the removal of element jackets, the treatment of uraxium -zirconium fuel elements, disposal into deep wells, the hydraulics of wells, thermal considerations of disposal aquifers regional hydrology, potential deep-well disposal areas in the U. S., aud the cost of disposal. (J.R.D.)
Date: June 13, 1957
Creator: de Laguna, W. & Blomeke, J. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dynamic Corrosion Screening Tests on Inconel and Nickel in NaCl-MgCl$sub 2$- UCl$sub 3$Bath

Description: Nickel is more susceptible to mass transfer ina 100hr nonisothermal dynamic corrosion system than is Inconel when exposed to a NaCl-MgCl/sub 2/-UCl/ sub 3/ (50.01800 F. No nickel mass transfer was observed in a 500hr test at 1350 F, but Inconel showed some attack under s transfer was observed in both tests, being more severe at the higher temperature. On the bases of these preliminary tests, it appears that nickel is a more satisfactory container than Inconel for the chloride bath at temperatur… more
Date: June 19, 1957
Creator: Jansen, D. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE EFFECT OF FLUCTUATIONS IN THE WIDTHS ON NEUTRON REACTION CROSS SECTIONS

Description: The general Wigner-Eisenbud theory is used to develop a method of analysis for the cross sections of fissionable nuclei. The method is employed in gdving a reasonable description of the low energy cross sections in U/sup 235/. The single level fit for U/sup 235/ is known to be unreasonable. Manylevel expressions for the cross sections are derived--the only approximation to the general theory being the neglect of all but a small group of resonances. It is shown that regardless of the number or d… more
Date: June 1, 1957
Creator: Dresner, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effects of Nuclear Weapons

Description: This handbook prepared by the Armed Forces Special Weapons Project of the Department of Defense in coordination with other cognizant government agencies and published by the United States Atomic Energy Commission, is a comprehensive summary of current knowledge on the effects of nuclear weapons. The effects information contained herein is calculated for yields up to 20 megatons and the scaling laws for hypothetically extending the calculations beyond this limit are given. The figure of 20 megat… more
Date: June 1, 1957
Creator: Glasstone, Samuel
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electrolytic Recycle Method for the Treatment of Radioactive Nitric Acid Waste. A Status Report at the Termination of the Project at KAPL

Description: A methed is descrihed for the treatment of radioactive neutralized nitric acid waste solutions. The process consists of electrolysis of sodium nitrate solutions and recycle the caustic formed to neutralize incoming nitric acid ate. Removal of a large fraction of the bulk inert substances by this method allows greater reductions in waste volume than conventional treatment by evaporation alone. Process chemistry studies show that a large fraction of the nitrate ion in alkaline solution can be ele… more
Date: June 26, 1957
Creator: Alter, H. W.; Barney, D. L.; Davidson, J. K.; Schafer, A. C., Jr. & Witt, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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