Computer simulation of stress corrosion cracking behavior of reactor pressure vessel (RPV) steels in light water reactor (LWR) environments in slow strain rate tests (SSRT)

Tetsuo Shoji, Shin ichi Moriya, Ken ichi Yoshida

Research output: Contribution to journalConference articlepeer-review

1 Citation (Scopus)

Abstract

Based upon a slip dissolution model, crack initiation and growth behavior of stress corrosion cracking of reactor pressure vessel steels, in pressurized high temperature water, was simulated by FEM (finite element method), with a combination of nodal force release techniques, simulating the crack growth by dissolution. Results obtained from the computer simulation for this materials/environment combination agree well with experiments in overall load/displacement curves of the tests and also can simulate crack initiation and propagation behavior. This computer simulation of slow strain rate (SSR) tests also focused on the significance of the multiple crack problems in SSR tests, particularly for smooth specimens, in relation to an evaluation of an actual crack tip strain rate. It was also found that crack growth rates, under such a multiple crack situation, can be uniquely plotted as a function of crack tip strain rates when evaluated correctly.

Original languageEnglish
Pages (from-to)44-46
Number of pages3
JournalASTM Special Technical Publication
Issue number1154
Publication statusPublished - 1992 Jan 1
EventSymposium on Computer Modeling for Corrosion - San Antonio, TX, USA
Duration: 1990 Nov 121990 Nov 13

ASJC Scopus subject areas

  • Engineering(all)

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