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Zirconium hydride reactor control reflector systems: summary report

Description: The beryllium reflector control system development for SNAP reactors is documented, from the initial SNAP 10A System through the current 5-kW(e) Thermoelectric System. Described are the various reflector concepts used in these systems for shadowshielded and 4 pi -shielded nuclear systems. The development of the key components, such as the actuators, bearings, and drive mechanisms for these systems, is also traced from the SNAP 10A concept through to the current system. Developmental test result… more
Date: June 30, 1972
Creator: Horton, P. H. & Kurzeka, W. J.
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The Zirconium-Hydrogen System at High Hydrogen Contents

Description: In order to elucidate the phase diagram of the Zr--H system at high hydrogen contents, a pressure-compositiontemperature study of this system in the temperature range 550 to 850 deg C was carried out from ZrH to ZrH/sub 2/. From the obtained isotherms, the position of the boundary between the two-phase ( beta + delta ) region and the single phase delta region was more precisely defined (where beta designates the hydrogen stabilized high temperature zirconium phase, and delta the cubic hydride p… more
Date: June 30, 1960
Creator: Libowitz, G. G.
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Zirconium Metal Fines Recovery: Interim Technical Report for May 15, 1950 to December 15, 1950

Description: This report covers the laboratory and pilot plant investigation of the reclamation of the low hafnium zirconium fines resulting from the manufacture of zirconium sponge and zirconium crystal bar. The process investigated involved recovery of the zirconium as zirconium tetrachloride, by drying the fines in an atmosphere of nitrogen and subsequent chlorination of the fines with anhydrous hydrogen chloride at temperatures above the sublimation point of the product.
Date: January 24, 1951
Creator: Ogburn, S. C., Jr. & Reader, L. J.
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Zirconium metal-water oxidation kinetics. I. Thermometry

Description: A description is given of the thermometry techniques used in the Zirconium Metal--Water Oxidation Kinetics Program. Temperature measurements in the range 900 to 1500$sup 0$C are made in three experimental systems: two oxidation apparatuses and the annealing furnace used in a corollary study of the diffusion of oxygen in $beta$-Zircaloy. Carefully calibrated Pt vs Pt--10 percent Rh thermocouples are employed in all three apparatuses, while a Pt--6 percent Rh vs Pt-- 30 percent Rh thermocouple an… more
Date: February 1, 1976
Creator: Cathcart, J. V.; McElroy, D. L.; Pawel, R. E.; Perkins, R. A.; Williams, R. K. & Yurek, G. J.
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Zirconium metal--water oxidation kinetics. II. Oxygen-18 diffusion in. beta. -Zircaloy

Description: The diffusion of oxygen-18 in ..beta..-Zircaloy-4 was measured from 900 to 1500/sup 0/C and survey measurements were made for ..beta..-zirconium and ..beta..-Zircaloy-2. The tracer diffusivity was measured over the entire temperature range and the chemical diffusivity from 1100 to 1500/sup 0/C. The experiments were performed by using oxygen-18 as the tracer and activating it by proton bombardment. Complementary measurements were also made using Auger Electron Spectroscopy. Results indicated tha… more
Date: July 1, 1976
Creator: Perkins, R. A.
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Zirconium metal-water oxidation kinetics. III. Oxygen diffusion in oxide and alpha Zircaloy phases. [BWR; PWR]

Description: The reaction of Zircaloy in steam at elevated temperature involves the growth of discrete layers of oxide and oxygen-rich alpha Zircaloy from the parent beta phase. The multiphase, moving boundary diffusion problem involved is encountered in a number of important reaction schemes in addition to that of Zircaloy-oxygen and can be completely (albeitly ideally) characterized through an appropriate model in terms of oxygen diffusion coefficients and equilibrium concentrations for the various phases… more
Date: October 1, 1976
Creator: Pawel, R. E.
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Zirconium metal-water oxidation kinetics. V. Oxidation of Zircaloy in high pressure steam. [PWR]

Description: A series of scoping tests to determine the influence of steam pressure on the isothermal oxidation kinetics of Zircaloy-4 PWR tubing was undertaken. The oxidation experiments were conducted in flowing steam at 3.45, 6.90, and 10.34 MPa (500, 1000, and 1500 psi) at 905/sup 0/C (1661/sup 0/F), and at 3.45 and 6.90 MPa at 1101/sup 0/C (2014/sup 0/F). A comparison of the results of these experiments with those obtained for oxidation in steam at atmospheric pressure under similar conditions indicate… more
Date: December 1, 1977
Creator: Pawel, R. E.; Cathcart, J. V.; Campbell, J. J. & Jury, S. H.
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Zirconium Oxide Nanostructures Prepared by Anodic Oxidation

Description: Zirconium oxide is an advanced ceramic material highly useful for structural and electrical applications because of its high strength, fracture toughness, chemical and thermal stability, and biocompatibility. If highly-ordered porous zirconium oxide membranes can be successfully formed, this will expand its real-world applications, such as further enhancing solid-oxide fuel cell technology. Recent studies have achieved various morphologies of porous zirconium oxide via anodization, but they hav… more
Date: January 1, 2008
Creator: Dang, Y. Y.; Bhuiyan, M.S. & Paranthaman, M. P.
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Zirconium Pheylarsonate Tracer Scale Method for the Differentiation of Pu(III) and Pu(IV) in Redox Solutions

Description: The following report studies an estimation of the amount of Pu(III) and Pu(IV) present in the IBP Stream, with the purpose of establishing an analytical, method suitable for routine control analysis. A method is discussed that is based on carrying Pu(IV) upon a zirconium phanylarsonate precipitate.
Date: June 30, 1948
Creator: Ice, C. H.
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Zirconium phosphate waste forms for low-temperature stabilization of cesium-137-containing waste streams

Description: Novel chemically bonded phosphate ceramics are being developed and fabricated for low-temperature stabilization and solidification of waste streams that are not amenable to conventional high-temperature stabilization processes because volatiles are present in the wastes. A composite of zirconium-magnesium phosphate has been developed and shown to stabilize ash waste contaminated with a radioactive surrogate of {sup 137}Cs. Excellent retainment of cesium in the phosphate matrix system was observ… more
Date: April 1, 1996
Creator: Singh, D.; Wagh, A.S. & Tlustochowicz
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Zirconium Pilot Plant Research and Development Progress Report

Description: The following progress report was compiled by the research and development division of the zirconium pilot plant. This report discusses two iodination and deposition runs that were completed as of August 20, 1951, as well as the third iodination run that uses a vaporizer condenser that condenses approximately 40 pounds of zirconium iodide.
Date: September 20, 1951
Creator: Accountius, O. E.; Black, D. G.; Dryden, C. E.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
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Zirconium Pilot Plant Research and Development Progress Report

Description: The following report studies the effect of flow rates and deposition pressure on the zirconium deposition in the zirconium pilot plant with the use of a Hilco oil purifier for the vacuum pumps that permitted studies to continue through the month.
Date: November 20, 1951
Creator: Dryden, C. E.; Accountius, O. E.; Black, D. G.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
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Zirconium Pilot Plant Research and Development. Progress Report

Description: A summary of the work which was done on the small pilot plant during the week's operation shows the following: (1) High vaporization rates can be obtained from a vibrating flash plate. (2) Feeding powder to the plate at a constant and controllable rate presented some difficulty. This may be overcome by pumping between Victoprene seals, proper outgassing of the powder, using a smaller diameter screw, and sloping the feed screw upward to avoid translation of the powder by vibration. (3) Depositio… more
Date: November 20, 1951
Creator: Dryden, C. E.; Accountius, O. E.; Black, D. G.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
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Zirconium-Precipitation Pilot Plant

Description: This report follows an investigation with the objectives to improve the design of an existing pilot plant to allow better control of operating variables than was attained by previous investigators, and to determine the effect of leaching time on phthalate recovery.
Date: September 30, 1950
Creator: Parish, G. T.; Bakal, R.; Goodman, E. I. & Larsen, H. A.
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Zirconium pressure tube testing: Test procedures, Production Assurance Program (Project H-700)

Description: UNC Nuclear Industries (UNC) has initiated a plan for the fabrication of zirconium alloy pressure tubes required for the future operation of N-Reactor. As part of this plan, UNC is establishing a program to qualify and develop a process capable of fabricating these pressure tubes to the requirements of UNC specification HWS 6502, REV. 4, Amendment 1. The objective of the Pressure Tube Testing Task is to support the UNC program-by performing physical, mechanical and chemical testing on prototype… more
Date: June 1, 1986
Creator: Zaloudek, F. R. & Lewis, M.
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Zirconium Purification Pilot Plant

Description: This report discusses the process of zirconium purification, providing an alternate method for converting ZrCl4 solution to the oxide in order to free it from small amounts of hafnium impurity that are naturally present.
Date: September 12, 1950
Creator: Lea, D. C.; Aykanian, A. A.; Abbanat, R. G. & Bowman, W. H.
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