A theoretical model for determination of fracture toughness of reactor pressure vessel steels in the transition region from automated ball indentation test

Thak Sang Byun, Jin Weon Kim, Jun Hwa Hong

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Abstract

A theoretical model is proposed to estimate the fracture toughness of ferritic steels in the transition region from ball indentation test data. The key concept of the model is that the indentation energy to a critical load is related to the fracture energy of the material. By applying the new model, the fracture parameters of reactor pressure vessel steel base and weld metals were estimated from the indentation load-depth curves. The estimated fracture stresses agreed well with those of the Wilshaw et al. model. The temperature dependence of the estimated KJC was almost the same as that of the ASTM KJC master curve. Also, the reference temperature obtained from the estimated KJC versus temperature curve correlated well with the index temperature of 41 J Charpy impact energy, T41 J. Additionally, the ball indentation deformation was simulated by ABAQUS code to evaluate the stress state and the result was compared with that at the crack tip.

Original languageEnglish
Pages (from-to)187-194
Number of pages8
JournalJournal of Nuclear Materials
Volume252
Issue number3
DOIs
StatePublished - Feb 1998
Externally publishedYes

Funding

The authors would like to thank Dr B.S. Lee, Mr J.H. Yoon and Mr J.H. Kim for supplying the fracture test and impact test data. This work is a part of the Advanced Nuclear Materials Development Program/Nuclear Structural Steels, which has been financially supported by the Korean Ministry of Science and Technology.

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