5-8 Nov 2013

IAEA, Vienna, Austria

Technical Meeting On Degradation Of Primary System Components Of Water Cooled Nuclear Power Plants: Current Issues And Future Challenges

The objectives of the Technical Meeting are to provide participants with information on the degradation of ferritic and stainless steels in reactor pressure vessels (RPVs), heads, core internals; piping steels, steam generators, and degradation of other components. Furthermore, the workshop will cover materials degradation issues for boiling water cooled reactors and other technological issues affecting the current fleet of light and heavy water cooled reactors. Based on the experts' presentations and discussions, priorities and gaps will be identified in research and technological areas.

Working Documents


Session 1-1. Effect of operating parameters. Session Chair: M. Cao (China)
  • Keynote: Detection of quasi-laminar hydrogen flaking indications in RPV forgings at the Belgian Doel3 and Tihange2
    Abstract, Presentation
    K. Oulid Dren, Belgium

  • Event investigation on leaks and cracks detected in the reactor coolant pressure boundary
    Presentation, Full paper
    A. Ballesteros, EC-JRC

  • Complex diagnostic assessment of the current status and remaining lifetime of primary components
    Abstract, Presentation
    M. Bakirov, Russia

  • Ageing management program - a tool to maintain NPP safety
    Abstract, Presentation
    O. Soloviov, Ukraine

Session 1-2
  • Keynote: Guidelines for integrity and lifetime assessment of components and piping in WWER NPPs during operation (VERLIFE)
    Abstract, Presentation
    M. Brumovsky, Czech Republic

  • EngInit - blueprint for an engineering model for time-to-failure of thin-walled, irradiated components of 316 SS under nominal PWR-relevant SCC conditions
    Abstract, Presentation
    M. Scibetta, Belgium

  • Current issues and challenges for irradiation embrittlement of RPVs in Korea
    Abstract, Presentation
    B. S. Lee, Korea R.

  • Metal degradation in Angra plants
    Presentation, Full paper
    J. Maneschy, Brazil

  • Specific degradations of main equipment of WWER-1000
    Abstract, Presentation
    D. Popov, Bulgaria

  • SNSA surveillance of primary components at Kr┼íko NPP
    Abstract, Presentation
    J. Skodlar, Slovenia

  • Degradation in Steam Generators
    Abstract, Presentation
    T. Burney, Pakistan

  • Analysis of the metal condition and resource assessment of RPV at Kozloduy NPP
    Presentation, Full paper
    E. Nicheva, Bulgaria

Session 2-1. Mechanisms governing the irradiation-induced embrittlement. Session Chair: T. Williams (UK), Co-Chair: N. Palm (USA)
  • Keynote: Correlation between microstructural & mechanical property changes in RPV materials of Greifswald Unit 4
    Full paper
    N. Soneda, Japan

  • Knowledge gaps in toughness and irradiation: lessons of the past, prospects for the future
    Abstract, Presentation
    T. Williams, UK

  • EDF R&D program on the ageing of reactor pressure vessel and its internals
    Abstract, Presentation
    A. Al Mazouzi, France

  • Irradiation induced damage of RPV steels studied by positron annihilation lifetime techniques
    Presentation, Full paper
    V. Slugen, Slovakia

  • The effect of microstructure on irradiation sensitivity
    Abstract, Presentation
    K. Wilford, UK

Session 2-2
  • Keynote: Major challenges for ensuring structural integrity of RPVs for extended service
    Presentation, Full paper
    R. Nanstad, USA

  • Flux effect analysis in WWER-440 reactor pressure vessel steels
    Abstract, Presentation A. Kryukov, Netherlands

  • Applicability of dose-damage relations to operating reactors
    Presentation, Full paper
    S. Ortner, UK

Session 2-3. Formation of irradiation-induced defects. Session Chair: P. Pareige (France), Co-Chair: L. Malerba (Belgium)
Session 3
Session 3-1
  • Radiation response of the overlay cladding from the decommisioned WWER-440 Greifswald Unit 4 RPV
    Presentation, Full paper
    H. W. Viehrig, M. Houska, E. Altstadt, Germany

  • Assessment of thermal ageing effects based on WWER-1000 SS data
    Abstract, Presentation
    A. Chernobaeva, Russia

  • Radiation damage in a high Ni weld
    Abstract, Presentation
    M. Kytka, M. Brumovsky, R. Kopriva, Czech Republic

  • Radiation damage in the IAEA reference material JRQ
    Abstract, Presentation
    R. Kopriva, M. Brumovsky, M. Kytka, Czech Republic

Session 3-2. Structural integrity evaluation, surveillance. Session Chair: H.W. Viehrig (Germany)
  • Structure integrity analysis of RPV during PTS - sensitivity study on the shape of postulated defect
    Presentation, Full paper
    M. Cao, China

  • Need for high fluence RPV reactor surveillance data for long term operation
    Abstract, Presentation
    W. L. Server, N. Palm, USA

  • Structural integrity evaluation for reactor vessel internals - Mexican experience
    Presentation, Full paper
    P. Ruiz Lopez, Mexico

  • Reactor vessel materials surveillance programme for a long term operation of a BWR
    Presentation, Full paper
    R. Hernandez Callejas, Mexico

Session 3-3. Metallurgical issues (inhomogeneities in material, fabrication history) and other LTO implications. Session Chair: M. Scibetta (Belgium)
  • Keynote: Is safe long term operation compatible with materials that are inhomogeneous?
    Abstract, Presentation
    M. Scibetta, Belgium

  • Some recent research results and their implications for RPV irradiation surveillance under LTO
    Abstract, Presentation, Full paper
    H. Hein, Germany

  • Assessment of the RPVs for long term operation in France
    Presentation, Full paper
    F. Balestreri, France

  • The Laguna Verde vessel material surveillance programme for long term operation
    Abstract, Presentation
    M. Gris Cruz, Mexico

Session 4-1

Please contact NENP Engineering Section - Contact Point if you have any questions.