A quantitative estimation of uncertainties involved in reactor pressure vessel steel transition temperature shift correlation

Philippe Van Asbroeck

    Research outputpeer-review

    Abstract

    The uncertainty on transition temperature shift data of irradiated pressure vessel steels is relatively important (o = 22°C). 70% of this uncertainty is explained by error during Charpy testing (10%), error on copper content (20%) error on irradiation temperature (20%) and fluence (20%). Improving the measurement techniques of copper content, irradiation temperature and fluence respectively by a factor 2 ; 2 and 3 implies that the major causes of uncertainty would in this case be the Charpy technique.
    Original languageEnglish
    Title of host publicationCAPRICE 79: Correlation accuracy in pressure vessel steel as reactor component investigation of change of material properties with exposure data
    Place of PublicationGermany
    PublisherIAEA - International Atomic Energy Agency
    Pages289-309
    Number of pages21
    StatePublished - 1979
    Event1979 - Meeting on accuracies in correlation between property change and exposure data from reactor pressure vessel steel radiation: IAEA - Juelich
    Duration: 24 Sep 197927 Sep 1979

    Conference

    Conference1979 - Meeting on accuracies in correlation between property change and exposure data from reactor pressure vessel steel radiation
    Abbreviated titleJUEL-CONF-37
    Country/TerritoryGermany
    CityJuelich
    Period1979-09-241979-09-27

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