Measurement of the fundamental parameters for the film-rupture/oxidation mechanism - The effect of chromium

S. A. Attanasio, J. S. Fish, W. W. Wilkening, P. M. Rosecrans, D. S. Morton, G. S. Was, Y. Yi

    Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

    16 Scopus citations

    Abstract

    Identification of the mechanism responsible for primary water stress corrosion cracking (PWSCC) in nickel-base alloys is a controversial topic. Numerous mechanisms, including the film-rupture/oxidation (i.e., slip-dissolution) mechanism, have been proposed to explain PWSCC. According to this mechanism, the observed sensitivity of PWSCC to material and environmental factors may be explained by the combined effects of repassivation kinetics, oxide rupture strain, and crack tip strain rate (which includes creep). Prior research has shown that increasing the Cr content of Ni-9%Fe-Cr from 16 to 30 wt% Cr strongly decreases SCC susceptibility. Consequently, measurements were performed for three film-rupture/oxidation mechanism subprocesses (repassivation, oxide rupture, and creep) as a function of Cr content, and SCC crack growth rate (CGR) predictions were made on the basis of the resulting data. Increasing the Cr level from 16 to 30 wt% was found to increase the rate of repassivation, increase the strain required to rupture the oxide film, and decrease the creep rate. Qualitatively, these data correctly predict a lower CGR for Alloy 690 (30 wt% Cr) than for Alloy 600 (16 wt% Cr). However, it is not clear whether the film-rupture/oxidation mechanism can quantitatively predict the observed CGRs for Alloy 600 at 338°C.

    Original languageBritish English
    Title of host publicationProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
    EditorsS. Bruemmer, P. Ford, G. Was
    PublisherMinerals, Metals and Materials Society
    Pages49-58
    Number of pages10
    ISBN (Print)0873394755, 9780873394758
    DOIs
    StatePublished - 1999
    EventProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors - - New Portbeach, CA, United States
    Duration: 1 Aug 19995 Aug 1999

    Publication series

    NameProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -

    Conference

    ConferenceProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
    Country/TerritoryUnited States
    CityNew Portbeach, CA
    Period1/08/995/08/99

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