Corrosion phenomena induced by supercritical water in Generation IV nuclear reactors

D. Guzonas, R. Novotny, S. Penttilä

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

    3 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
    Number of pages48
    ISBN (Electronic)9780081009123
    ISBN (Print)978-0-08-100906-2
    Publication statusPublished - 27 Sep 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


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