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Onizawa, Kunio; Van Walle, E.*; Pavirich, W.*; Nanstad, R.*
NUREG/CR-6777, 81 Pages, 2002/08
no abstracts in English
Tobita, Toru; Otsu, Takuyo*; Takamizawa, Hisashi; Nishiyama, Yutaka
no journal, ,
When the reactor pressure vessel has been subjected to the pressurized thermal shock event, even if an non-ductile crack occurs from the postulated defect at the inner surface of the reactor pressure vessel, the crack may stop before penetrates the vessel wall. In this report, crack-arrest fracture toughness (K) tests were performed on the three types of reactor pressure vessel steels with different mechanical properties. It was confirmed that the temperature dependency of K follows the Master Curve as well as static fracture toughness. In addition, we examined the correlation between the crack-arrest fracture toughness and crack arrest force of instrumentation Charpy test.