A Study of Oxide Film Breakdown on Zirconium Alloys by Capacitance Measurements PDF Download
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Author: Atomic Energy of Canada Limited
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Category :
Languages : en
Pages :
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Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Author:
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 988
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Author:
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Category : Aeronautics
Languages : en
Pages : 308
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Author: R. D. Misch
Publisher:
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Category : Metals
Languages : en
Pages : 32
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Zirconium anodizes similarly to tungsten in respect to the change of interference colors with applied voltage. However, the oxide layer on tungsten cannot reach as great a thickness. Hafnium does not anodize in the same way as zirconium but is similar to tantalum. By measuring the interference color and capacitative thicknesses on zirconium (Grades I and III) and a 2.5 wt.% tin alloy, the film was found to grow less rapidly in terms of capacitance than in terms of interference colors. This was interpreted to mean that cracks develop in the oxide as it thickens. The effect was most pronounced on Grade III zirconium and least pronounced on the tin alloy. The reduction in capacitative thickness was especially noticeable when white oxide appeared. Comparative measurements on Grade I zirconium and 2.5 wt.% tin alloy indicated that the thickness of the oxide film on the tin alloy (after 16 hours in water) increased more rapidly with temperature than the film on zirconium. Tin is believed to act in ways to counteract the tendency of the oxide to form cracks, and to produce vacancies which promote ionic diffusion.
Author: U.S. Atomic Energy Commission. Division of Technical Information
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Category : Nuclear energy
Languages : en
Pages : 932
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Author:
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Category : Nuclear energy
Languages : en
Pages : 36
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Series consists of individual technical reports.
Author: J. N. Wanklyn
Publisher:
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Category : Zirconium alloys
Languages : en
Pages : 18
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Several attempts to develop zirconium alloys suitable for use in superheated steam have been described (1-4). Assessment (5,6) of the results suggested that although a number of alloying additions can have a beneficial effect, great variability confuses the results, which, moreover, are no better than would be achieved by unalloyed zirconium in dry oxygen. Further, it appeared that only a low concentration of the added elements, provided it was distributed appropriately in the oxide film, might suffice to give corrosion resistance (2); it was also suggested (6) that the significant film breakdown in steam occurred on a very small scale. The behavior of resistant alloys was pictured in terms of a balance between film growth and film breakdown, leading beyond weight gains of 100 mg/dm2 to a more or less linear rate of corrosion. This paper reports recent attempts to study these two processes more intimately, using thinner films on unalloyed zirconium, and exploring some newer techniques. It may be said that zirconium, quite apart from its nuclear interest, is a rather suitable metal for such studies, forming but one oxide and having only a single valence. Moreover, although the entry of small amounts of hydrogen into the oxide is important, the complication of hydrated oxides is absent. Inasmuch as the aim is to give an up-to-date report of current work and thought, loose ends and tentative explanations may be expected in the following account.
Author:
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Category : Hafnium
Languages : en
Pages : 40
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Category : Energy development
Languages : en
Pages : 40
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Author: Gabriell Ilevbare
Publisher: Springer
ISBN: 3319487604
Category : Technology & Engineering
Languages : en
Pages : 2354
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Book Description
This 15th Edition of the International Conference on Materials Degradation in Light Water Reactors focuses on subject areas critical to the safe and efficient running of nuclear reactor systems through the exchange and discussion of reseach results as well as field operating and management experience.
