UDC 539.4 Transferability of Laboratory Fracture Data to Safety Assessment of Postulated Defects in Critical NPP Components
نویسندگان
چکیده
С целью оценки прочности корпусов реакторов АЭС проведены натурные стендовые испы тания на трещиностойкость образцов с внутренними дефектами. Представленные резуль таты свидетельствуют о возможности использования в расчетах полученных стандарт ных данных для обнаруженных и предполагаемых дефектов корпусных сталей. Показано, что применение метода "Master Curve” обеспечивает более точное прогнозирование усло вий вязкохрупкого перехода, чем подходы, использующие характеристику KIc в зависимости от RTndt.
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