Corrosion phenomena induced by supercritical water in Generation IV nuclear reactors

D. Guzonas, R. Novotny, Sami Penttilä

    Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

    7 Citations (Scopus)


    The various supercritical water-cooled reactor concepts being developed under the Generation IV International Forum are the natural evolution of the water-cooled reactor technology that has successfully supplied the majority of nuclear-based electricity since the dawn of commercial nuclear power generation. The materials challenges that must be addressed in the development of a supercritical water-cooled reactor are in most respects the same as those experienced by the current generations of water-cooled reactors. This chapter summarizes current knowledge of corrosion and environmentally assisted cracking phenomena under the conditions expected in the core of a supercritical water-cooled reactor, with an emphasis on recent advances in experiment and modeling.
    Original languageEnglish
    Title of host publicationStructural Materials for Generation IV Nuclear Reactors
    EditorsPascal Yvon
    PublisherWoodhead Publishing
    ISBN (Print)978-0-08-100906-2
    Publication statusPublished - 27 Sept 2016
    MoE publication typeD2 Article in professional manuals or guides or professional information systems or text book material

    Publication series

    SeriesWoodhead publishing series in energy


    • corrosion
    • environmentally assisted cracking
    • mechanism
    • nickel-based alloy
    • steel
    • supercritical water


    Dive into the research topics of 'Corrosion phenomena induced by supercritical water in Generation IV nuclear reactors'. Together they form a unique fingerprint.

    Cite this