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Corrosion of Ticode-12 in A Simulated Waste Isolation Pilot Project (Wipp) Brine*

Published online by Cambridge University Press:  21 February 2011

T. M. Ahn ,
B. S. Lee ,
J. Woodward ,
R. L. Sabatini  and
P. Soo
T. M. Ahn
Affiliation:
Brookhaven National Laboratory, Upton, NY 11973
B. S. Lee
Affiliation:
Brookhaven National Laboratory, Upton, NY 11973
J. Woodward
Affiliation:
Brookhaven National Laboratory, Upton, NY 11973
R. L. Sabatini
Affiliation:
Brookhaven National Laboratory, Upton, NY 11973
P. Soo
Affiliation:
Brookhaven National Laboratory, Upton, NY 11973
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Abstract

The corrosion behavior of TiCode-12 (Ti-0.3 Mo-0.8 Ni) high level nuclear waste container alloy has been studied for a simulated WIPP brine at a temperature of 150°C or below. Crevice corrosion was identified as a potentially important failure mode for this material. Within a mechanical crevice, a thick oxide film was found and shown to be the rutile form of TiO2, with a trace of lower oxide also present. Acidic conditions were found to cause a breakdown of the passive oxide layer. Solution aeration and increased acidity accelerate the corrosion rate. In hydrogen embrittlement studies, it was found that hydrogen causes a significant decrease in the apparent stress intensity level in fracture mechanics samples. Hydride formation is thought to be responsible for crack initiation. Stress corrosion cracking under static loads was not observed. Attention has also been given to methods for extrapolating short term uniform corrosion rate data to extended times.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 15: Symposium D – Scientific Basis for Nuclear Waste Management VI , 1982 , 761
Copyright
Copyright © Materials Research Society 1983

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Footnotes

*

This work was performed under the auspices of the U.S. Nuclear Remulatory Commission.

References

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