The corrosion behavior of hafnium in high-temperature-water environments

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The high-temperature-water corrosion performance of hafnium is evaluated. Corrosion kinetic data are used to develop correlations that are a function of time and temperature. The evaluation is based on corrosion tests conducted in out-of-pile autoclaves and in out-of-flux locations of the Advanced Test Reactor (ATR) at temperatures ranging from 288 to 360 C. Similar to the corrosion behavior of unalloyed zirconium, the high-temperature-water corrosion response of hafnium exhibits three corrosion regimes: pretransition, posttransition, and spalling. In the pretransition regime, cubic corrosion kinetics are exhibited, whereas in the posttransition regime, linear corrosion kinetics are exhibited. Because of the scatter in the ... continued below

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47 p.

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Rishel, D.M.; Smee, J.D. & Kammenzind, B.F. October 1, 1999.

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  • Bettis Atomic Power Laboratory
    Publisher Info: Bettis Atomic Power Lab., West Mifflin, PA (United States)
    Place of Publication: West Mifflin, Pennsylvania

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Description

The high-temperature-water corrosion performance of hafnium is evaluated. Corrosion kinetic data are used to develop correlations that are a function of time and temperature. The evaluation is based on corrosion tests conducted in out-of-pile autoclaves and in out-of-flux locations of the Advanced Test Reactor (ATR) at temperatures ranging from 288 to 360 C. Similar to the corrosion behavior of unalloyed zirconium, the high-temperature-water corrosion response of hafnium exhibits three corrosion regimes: pretransition, posttransition, and spalling. In the pretransition regime, cubic corrosion kinetics are exhibited, whereas in the posttransition regime, linear corrosion kinetics are exhibited. Because of the scatter in the spalling regime data, it is not reasonable to use a best fit of the data to describe spalling regime corrosion. Data also show that neutron irradiation does not alter the corrosion performance of hafnium. Finally, the data illustrate that the corrosion rate of hafnium is significantly less than that of Zircaloy-2 and Zircaloy-4.

Physical Description

47 p.

Notes

INIS; OSTI as DE00755333

Medium: P; Size: 47 pages

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  • Journal Name: Journal of Nuclear Materials; Other Information: Submitted to Journal of Nuclear Materials

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  • Report No.: B-T-3232
  • Grant Number: AC11-98PN38206
  • Office of Scientific & Technical Information Report Number: 755333
  • Archival Resource Key: ark:/67531/metadc710536

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Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • October 1, 1999

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • April 12, 2017, 6:54 p.m.

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Rishel, D.M.; Smee, J.D. & Kammenzind, B.F. The corrosion behavior of hafnium in high-temperature-water environments, article, October 1, 1999; West Mifflin, Pennsylvania. (digital.library.unt.edu/ark:/67531/metadc710536/: accessed May 25, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.