PWSCC initiation of alloy 600: Effect of long-term thermal aging and triaxial stress

Seung Chang Yoo, Kyoung Joon Choi, Seunghyun Kim, Ji Soo Kim, Byoung Ho Choi, Yun Jae Kim, Jong Sung Kim, Ji Hyun Kim

    Research output: Chapter in Book/Report/Conference proceedingConference contribution

    Abstract

    Thermally aged nickel based Alloy 600 was investigated to evaluate the effects of long-term thermal aging and triaxial stress on primary water stress corrosion crack initiation behavior. Long-term thermal aging was simulated by heat treatment at 400, °C, a temperature that does not cause excessive formation of second phases that cannot form in nuclear power plant service conditions. Triaxial stress was applied by a round notch in the gauge length of some test specimen; other specimens were smooth. Slow strain rate tests (SSRT) monitored by the direct current potential drop method were conducted to evaluate stress corrosion crack initiation susceptibility of the thermally aged specimens in the primary water environment. For smooth specimens (which experience uniaxial stress), the susceptibility of those thermally aged for the equivalent of 10-years was the highest, while the susceptibility of the as-received specimens was the lowest. However, for the notched specimens (which experience triaxial stress), the specimens thermally aged for the equivalent of 20-years showed the highest susceptibility, while the as-received specimens showed the lowest.

    Original languageEnglish
    Title of host publicationProceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
    EditorsDenise Paraventi, Michael Wright, John H. Jackson
    PublisherSpringer International Publishing
    Pages281-292
    Number of pages12
    ISBN (Print)9783319672434
    DOIs
    Publication statusPublished - 2018
    Event18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 - Portland, United States
    Duration: 2017 Aug 132017 Aug 17

    Publication series

    NameMinerals, Metals and Materials Series
    VolumePart F9
    ISSN (Print)2367-1181
    ISSN (Electronic)2367-1696

    Other

    Other18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
    Country/TerritoryUnited States
    CityPortland
    Period17/8/1317/8/17

    Bibliographical note

    Funding Information:
    Acknowledgements This work was financially supported by the Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KOFONS), granted financial resource from the Nuclear Safety and Security Commission (NSSC), Republic of Korea (No. 1403006) and by the Human Resources Development of the Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea Government Ministry of Trade Industry and Energy (MOTIE) (No. 20174030201430).

    Publisher Copyright:
    © The Minerals, Metals & Materials Society 2018.

    Keywords

    • Nickel based alloy
    • Primary water stress corrosion cracking
    • Thermal aging
    • Triaxial stress

    ASJC Scopus subject areas

    • Electronic, Optical and Magnetic Materials
    • Energy Engineering and Power Technology
    • Mechanics of Materials
    • Metals and Alloys
    • Materials Chemistry

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