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VVER long-term operation – A review based on the material studies results from past and ongoing EU-supported research projects

  • Vladimir Slugen*
  • , Jana Simeg Veternikova
  • , Maria Domankova
  • , Matus Gavalec
  • , Jana Petzova
  • , David Slnek
  • , Mykola Dzubinsky
  • , Oleksii Shugaylo
  • , Ildiko Szenthe
  • , Ferenc Gillemot
  • , Maksym Zarazovskii
  • , Jari Lydman
  • , Radim Kopriva
  • , Szabolcs Szavai
  • , Ondrej Srba
  • *Corresponding author for this work
    • Slovak University of Technology
    • VUJE a.s.
    • European Commission
    • State Scientific and Technical Center for Nuclear and Radiation Safety (SSTC NRS)
    • HUN-REN Centre for Energy Research (HUN-REN EK)
    • IPP Centre LLC
    • ÚJV Řež a.s.
    • Bay Zoltán Nonprofit Ltd. for Applied Research (BZN)
    • Research Centre Řež

    Research output: Contribution to journal › Review Article › peer-review

    Abstract

    Safe and long-term operation (LTO) of nuclear power plants (NPP) with Water-Water Energetic Reactors (VVER) is essential for several central and eastern European countries to keep their energy supply security. During the last decades, several EU-supported projects in framework projects or Horizon2020 schemes have focused on the material degradation of pressurised water reactors (PWRs), especially VVERs. This paper aims to extract the most important results dominantly from EURATOM projects which support or could limit the long-term operation of this Soviet design of PWRs. The accent is given on ongoing projects such as FRACTESUS, STRUMAT-LTO, APAL, and ENTENTE. Actually, running project DELISA-LTO (2022–2026) comprises not only results from previous research in this area but also incorporates wide material databases coming from nuclear power plant V-1 in Jaslovské Bohunice (Slovakia), which was shut down after 28 years of operation and provides wide-range of original service-aged materials specimens for profound material studies having in mind lifetime extension of VVERs. Consolidated knowledge focused mainly on the reactor pressure vessel (RPV) material studies is summarised and supported by relevant references.

    Original languageEnglish
    Article number113949
    JournalNuclear Engineering and Design
    Volume435
    DOIs
    Publication statusPublished - 15 Apr 2025
    MoE publication typeA2 Review article in a scientific journal

    Funding

    The authors would like to thank the European Union Project DELISA-LTO (No.101061201) for financial support.

    Keywords

    • European projects
    • Long-term operation
    • Material research
    • Swelling
    • Thermal ageing
    • VVER technologies

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