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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Article
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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.
Item Type: Refine your search to only Report
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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
Item Type: Refine your search to only Article
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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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Zirconium Research and Development : Progress Report

Description: From introduction: "This is the ninth monthly report, BMI-514, under Contract No. AT(30-1)-771 on "Zirconium Research and Development". The report covers the work period from September 15, 1950, to October 15, 1950. Work is continuing on the preparation of large-diameter zirconium crystal bars in the 16-inch-diameter de Boer unit. Crystal bars up to 1-5/16 inches in diameter and 8 feet long have been prepared in this unit."
Date: October 15, 1950
Creator: Bulkowski, H. H.; Sebenick, J. J.; Campbell, Ivor E. & Gonser, B. W.
Item Type: Refine your search to only Report
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ZIRCONIUM RESEARCH AND DEVELOPMENT. Progress Report No. 9 for September 15, 1950 to October 15, 1950

Description: A zirconium crystal bar, weighing 29 pounds and 1 5/16 inches in diameter by 8 feet in over-all length, was prepared, using pear-shaped zirconium couples to join the filament to the electrodes. This crystal bar was the largest produced to date in the 16-in.-diam. de Boer unit. The design of the couplings was modified to incorporate improvements indicated by the initial run, and another run is in progress. Binary alloys of Zr and Ni, Cr, and Si, as well as a zirconium alloy containing Fe, Al, an… more
Date: October 15, 1950
Creator: Bulkowski, H.H.; Sebenick, J.J.; Campbell, I.E. & Gonser, B.W.
Item Type: Refine your search to only Report
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Zirconium-titanium phosphate acid catalysts synthesized by sol gel techniques

Description: Recently a large effort has been put into identifying solid acid materials, particularly sulfated zirconia and other sulfated metal oxides, that can be used to replace environmentally hazardous liquid acids in industrial processes. The authors are studying a group of mixed metal phosphates, some of which have also been sulfated, for their catalytic and morphological characteristics. Zirconium and titanium are the metals used in this study and the catalysts are synthesized from alkoxide starting… more
Date: March 1, 1998
Creator: Jackson, N. B.; Thoma, S. G.; Kohler, S. & Nenoff, T. M.
Item Type: Refine your search to only Article
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Zirconium Tube Rupture from Localized Overheating

Description: Very little information and data are available on the various physical properties of Zircaloy tubing, especially the high temperature- high pressure failure aspects. As greater use is being made of the low cross-sectional properties of this material in the design and development of reactor components, it was considered desirable to determine the type of failure that would be experienced under conditions of a localized over-heating. This hot-spot could be caused by "cocked" or warped fuel elemen… more
Date: September 9, 1959
Creator: Jackson, P. M.
Item Type: Refine your search to only Report
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Zirconium tube sample evaluation program

Description: This document, dated May 3, 1966, presents data from the zirconium tube sample evaluation program at the Hanford Reservation. Data presented includes: (1) operating history, (2) flow characteristics, (3) time in core, and (4) average temperature for numerous samples. The document consists entirely of data.
Date: May 3, 1966
Creator: Korpi, W.E.
Item Type: Refine your search to only Report
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Zircons and fluids: An experimental investigation with applications for radioactive waste disposal

Description: The long-term stability of nuclear waste forms or barriers is related to changes in physical properties of the material induced through radiation damage and subsequent changes in solubility. Investigations conducted by us on natural zircons (ZrSiO{sub 4}) supports a positive correlation between level of alpha damage and fluid composition to enhanced levels of corrosion. New data are presented on the nature and rate of the solution process. We also present data on our continuing efforts to synth… more
Date: 1992~
Creator: Sinha, A.K.; Student, J. & Essex, R.
Item Type: Refine your search to only Report
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Zircons and fluids: An experimental investigation with applications for radioactive waste disposal. Stability of zircons: Progress report, January 1992--December 1992

Description: The long-term stability of nuclear waste forms or barriers is related to changes in physical properties of the material induced through radiation damage and subsequent changes in solubility. Investigations conducted on natural zircons (ZrSiO{sub 4}) supports a positive correlation between level of alpha damage and fluid composition to enhanced levels of corrosion. In this report we present preliminary data on the nature and rate of the solution process involving < 600,000 year-old zircons being… more
Date: 1993~
Creator: Sinha, A. K.
Item Type: Refine your search to only Report
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Zircons and fluids: An experimental investigation with applications for radioactive waste storage. Final report, July 1, 1988--July 31, 1994

Description: The project objective was to develop a relationship between the stability of zircons (both natural and synthetic) with variable levels of radiation damage to fluids because of the clear relationship between enhanced solubility (leachability) and {alpha} - damage, our research was able to quantify this process. We also analyzed the mechanics of fractures induced due to both radiation and temperature enhanced stresses. Both objective were successfully carried out, and although details are availab… more
Date: May 1, 1998
Creator: Sinha, A.K.
Item Type: Refine your search to only Report
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The Zirflex Decladding of Tube-in-Tube Type Fuel Elements

Description: Pilot unit Zirflex dissolutions were carried out on near prototypical tube-in-tube type elements clad in oxidized Zircaloy. The runs were made with the elements horizontal and at simulated large scale operating conditions. No significant difference was noted between the actual decladding achieved in these experiments and that which was predicted from prior studies on similarly oxidized elements with somewhat different geometries. No gas blanketing nor diffusion effects were observed. Initially,… more
Date: February 23, 1961
Creator: Smith, P. W.
Item Type: Refine your search to only Report
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Zirflex Dissolution of the Annular Cladding of Simulated Power Fuel Elements

Description: A study was conducted to compare the estimated dissolution rate of Zircaloy-2 clad annular fuel elements on the fully expesed metal with that in the annuli. Results indicate that decladding of these elements should proceed uniformly on all surfaces. Heat balance data from the study are also reported. (J.R.D.)
Date: December 1, 1959
Creator: Smith, P. W.
Item Type: Refine your search to only Report
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