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).
|Number of pages||7|
|Journal||American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP|
|Publication status||Published - 1994 Dec 1|
|Event||Proceedings of the 1994 Pressure Vessels and Piping Conference. Part 2 (of 19) - Minneapolis, MN, USA|
Duration: 1994 Jun 19 → 1994 Jun 23
ASJC Scopus subject areas
- Mechanical Engineering