Improvement of predictive capability of environmentally assisted cracking by means of computer simulation of crack propagation

Tetsuo Shoji, S. Moriya, H. Arai, M. Higashi

Research output: Contribution to journalConference article

3 Citations (Scopus)

Abstract

It is of practical importance to predict the stress corrosion crack (SCC) crack growth behavior in the pressure boundary components of nuclear power plants during operation. The establishment of the prediction method of SCC initiation and growth in light water reactor (LWR) environment is one of the essential steps in structural integrity assessment. In this paper, based upon a dissolution model, crack growth behavior of stress corrosion cracking of reactor pressure vessel steel of SA533B in simulated LWR environment under monotonic rising load (in other words Slow Strain Rate Test) and constant loading was simulated by the combination of FEM stress-strain analysis on growing crack and dissolution model. From the simulation results, the relationship between crack tip strain rate and crack propagation rate was discussed quantitatively. Crack growth rate can be evaluated in terms of both the crack tip strain rate and the crack tip solution chemistry such as, sulfur concentration and steady state dissolution rate (ISS).

Original languageEnglish
Pages (from-to)107-113
Number of pages7
JournalAmerican Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume287
Publication statusPublished - 1994 Dec 1
EventProceedings of the 1994 Pressure Vessels and Piping Conference. Part 2 (of 19) - Minneapolis, MN, USA
Duration: 1994 Jun 191994 Jun 23

ASJC Scopus subject areas

  • Mechanical Engineering

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