Vergleichsanalysen zur Integrität von Reaktordruckbehältern vom Typ WWER-440

Translated title of the contribution: Comparative analyses of the integrity of reactor pressure vessels, type WWER-440

Jurgen Sievers, Heli Talja, X. Liu, A. Tutnov, Heikki Raiko

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

    Abstract

    Different FE models and programs were used to study the load of a RPV with an assumed partial circumferential crack in the near-core circumferential weld seam as a result of a mixing transient with temporal variation of coolant temperature in the axial and circumferential directions. Results tallied well with crack loads calculated by elasto-plastic FE analyses. Comparative calculations were performed involving simplified thermo-mechanical load assumptions, while assuming rotational-symmetric or strip-wise cooling at a RPV featuring assumed circumferential cracks of different depths and geometries.
    Translated title of the contributionComparative analyses of the integrity of reactor pressure vessels, type WWER-440
    Original languageGerman
    Title of host publicationSicherheit und Verfügbarkeit in der Anlagentechnik mit dem Schwerpunkt Kerntechnik
    Subtitle of host publicationThemenschwerpunkt: Komponentensicherheit
    Place of PublicationStuttgart
    PublisherMaterials Testing Institute University of Stuttgart MPA
    Number of pages52
    Publication statusPublished - 1993
    MoE publication typeB3 Non-refereed article in conference proceedings
    Event19. MPA-seminar Sicherheit und Verfügbarkeit in der Anlagentechnik - Stuttgart, Germany
    Duration: 7 Oct 19938 Oct 1993

    Conference

    Conference19. MPA-seminar Sicherheit und Verfügbarkeit in der Anlagentechnik
    CountryGermany
    CityStuttgart
    Period7/10/938/10/93

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  • Cite this

    Sievers, J., Talja, H., Liu, X., Tutnov, A., & Raiko, H. (1993). Vergleichsanalysen zur Integrität von Reaktordruckbehältern vom Typ WWER-440. In Sicherheit und Verfügbarkeit in der Anlagentechnik mit dem Schwerpunkt Kerntechnik: Themenschwerpunkt: Komponentensicherheit Materials Testing Institute University of Stuttgart MPA.