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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
open access

Zirflex Dissolution of the Annular Cladding of Simulated Power Fuel Elements

Description: The current interest in a tube-in-tube type Zircaloy-2 clad UO2 fuel element for use in the power reactors provided the incentive for a study of the dissolution of cladding from an annular space. The objectives of the study were to compare the estimated rate of dissolution in the annuli with rates on fully exposed metal. Because of an interest from the design standpoint, heat balance data from the study are reported.
Date: December 9, 1959
Creator: Smith, P. W.
Item Type: Refine your search to only Report
open access

The Zirflex- Interim Development Summary

Description: The processing of spent fuels from nuclear power and propulsion reactors is planned by Hanford Atomic Products Operation as part of the Atomic Energy Commission's interim processing scheme. The spent nuclear fuels have cores of UO2, U, or alloys of U-Mb, U-Al, or U-Zr clad in either stainless steel, aluminum, or Zircaloy. This report discusses only the Zircaloy-clad fuels and the applications of the Zirflex Process for dissolution. Zirflex chemical flow sheets are presented as developed by pilo… more
Date: June 24, 1959
Creator: Platt, A. M. & Cooley, C. R.
Item Type: Refine your search to only Report
open access

The Zirflex Process

Description: tive dissolution of zirconium or Zircaloy fuel cladding. The process involves the dissolution of the cladding material in solutions of ammonium fluoride alone or in mixture with amonium nitrate. Mixtures of amonium fluoride and amonium nitrate are preferred since they result in very little evolution of hydrogen during the is that these solutions attack austenitic stainless steels only slowly, in sharp contrast to the media (e.g., hydrofluoric acid or hydrofluoric-nitric acid mixtures) generng 6… more
Date: October 31, 1958
Creator: Swanson, J. L.
Item Type: Refine your search to only Report
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THE ZIRFLEX PROCESS INTERIM DEVELOPMENT SUMMARY

Description: The Zircaloy-clad fuels and the application of the Zirflex Process for dissolution are discussed. Zirflex chemical flowsheets are presented as developed by pilot plant operatlons. The Zirflex Process is applicable to the reprocessing of fuels from the Dresden Reactor and the PWR Reactor. Other applications of the process are the Plutonium Recycle Test Reactor fuels and the New Production Reactor fuels, possible fuels from the Experimental Breeder Reactor; NPD-2 fuels; and fuels from Carolina-Vi… more
Date: June 24, 1959
Creator: Platt, A.M. & Cooley, C.R.
Item Type: Refine your search to only Report
open access

THE ZIRFLEX PROCESS TERMINAL DEVELOPMENT REPORT

Description: The Zirflex Process employs a boiling aqueous solution of ammonium fluoride and ammonium nitrate to dissolve zirconium or Zircaloy. Average unoxidized Zircaloy dissolution rates are from 10 to 15 mils/hr for the optimum charge solution of 5.5M NH/sub 4/F-0.5M NH/sub 4/NO/sub 3/ at a F/Zr mole ratio of 7. Zircaloy, which is oxidized by exposure to high-temperature air or water, dissolves at rates of threeto five-fold less. Cores of uranium, uranium- aluminum, and uranium dioxide are not severely… more
Date: September 20, 1960
Creator: Smith, P.W.
Item Type: Refine your search to only Report
open access

Zivotofsky v. Kerry: The Jerusalem Passport Case

Description: This report briefly describes legislative efforts to modify U.S. policy with respect to Jerusalem, in particular multiple enactments of the passport provision. The report summarizes the appellate court's opinion finding the passport measure unconstitutional and presents brief synopses of the petitioner's argument before the Supreme Court, the Secretary of State's brief in response, and briefs of amici curiae submitted by the Senate (pursuant to S.Res. 504) and by some Members of the House of Re… more
Date: October 30, 2014
Creator: Elsea, Jennifer K.
Item Type: Refine your search to only Report
open access

Zivotofsky v. Kerry: The Jerusalem Passport Case and Its Potential Implications for Congress's Foreign Affairs Powers

Description: This report briefly describes legislative efforts to modify U.S. policy with respect to Jerusalem, in particular multiple enactments of the passport provision. The report then summarizes the Supreme Court decision, including concurrences and dissents. Finally, the report concludes by suggesting possible implications of the decision with respect to Congress's authority to influence foreign affairs.
Date: September 28, 2015
Creator: Elsea, Jennifer K.
Item Type: Refine your search to only Report
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