Application of the local fracture stress model on the cleavage fracture of the reactor pressure vessel steels in the transition temperature region

Won Jon Yang, Bong Sang Lee, Moo Young Huh, Jun Hwa Hong

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    20 Citations (Scopus)

    Abstract

    The fracture toughness in the ductile-brittle transition region of reactor pressure vessel steels was evaluated by means of an RKR-type model which describes the temperature dependence of the cleavage fracture toughness based on the constant fracture stress σf. The fracture stress σf and the characteristic distance are two main parameters in the RKR model. In order to apply the RKR model to the transition temperature region, these two parameters were investigated in different manners. In this study, the local fracture stress, σf*, was determined from the pre-cracked specimens. The results showed that the local fracture stress σf* determined from the pre-cracked specimens was higher than the fracture stress σf from the notched specimens, while those values were practically independent of the temperatures. The CID (cleavage initiation distance), which represents the distance from the crack tip to the cleavage initiation site, was measured in every fractured specimen. The measured CID values were strongly dependent on the test temperatures. Besides, the fracture toughness KJC in the transition region was dependent on the measured CID. The RKR model, when the local fracture stress σf* and the measured CIDs were applied, could describe the temperature dependency of the median transition fracture toughness KJC(med).

    Original languageEnglish
    Pages (from-to)234-242
    Number of pages9
    JournalJournal of Nuclear Materials
    Volume317
    Issue number2-3
    DOIs
    Publication statusPublished - 2003 May 1

    Bibliographical note

    Funding Information:
    This work has been financially supported by the Korean Ministry of Science of Technology through the Reactor Pressure Boundary Materials Project.

    ASJC Scopus subject areas

    • Nuclear and High Energy Physics
    • General Materials Science
    • Nuclear Energy and Engineering

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