Evaluation of mechanical and environmental parameters affecting primary water stress corrosion cracking of nickel-based alloys

Junhyun Kwon, Yong Sun Yi, Joung Soo Kim

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

    4 Scopus citations

    Abstract

    Primary water stress corrosion cracking (PWSCC) is one of the main degradation processes of nickel-based alloys in the pressurized water reactor environments. This paper evaluates the effects of the mechanical and environmental parameters on the cracking behavior of Alloy 600 in a quantitative way. Based on two mechanistic models for SCC, including the slip oxidation (SO) and internal oxidation (10) mechanism, we have formulated the equations for the crack growth rate (CGR) calculation. The concept of a crack-tip strain rate was embedded into the CGR equation for the 10 model, as well as for the SO model, which enables us to predict the CGR. It is found that the proposed two CGR equations are of use in predicting the CGRs of Alloy 600 in high temperature water environments. Particularly, the use of oxygen diffusion rate embedded in the 10 model equation produces the comparable CGRs to the measured data. From the parametric study, the significance of the mechanical parameters on the cracking behavior was examined. Since a variation of the yield strength and the strain-hardening exponent of metals might enhance or reduce the CGR, it is of importance to accurately determine the mechanical parameters. In evaluating the effect of the water chemistry on the CGR, only the SO model equation was used since the IO model dose not take the water chemistry parameters into account at present.

    Original languageBritish English
    Title of host publicationProceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
    Pages661-668
    Number of pages8
    StatePublished - 2005
    Event12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors - Salt Lake City, UT, United States
    Duration: 14 Aug 200518 Aug 2005

    Publication series

    NameProceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

    Conference

    Conference12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
    Country/TerritoryUnited States
    CitySalt Lake City, UT
    Period14/08/0518/08/05

    Keywords

    • Crack growth rate
    • Internal oxidation
    • Primary water stress corrosion cracking
    • Slip oxidation

    Fingerprint

    Dive into the research topics of 'Evaluation of mechanical and environmental parameters affecting primary water stress corrosion cracking of nickel-based alloys'. Together they form a unique fingerprint.

    Cite this