Abstract
It is an important issue to predict Stress corrosion crack growth behavior in the pressure boundary components of nuclear power plants during operation. The establishment of a prediction method of SCC crack initiation and growth in LWR environment is one of the essential steps for structural integrity assessment. In this paper, growth behavior of stress corrosion cracking in a reactor pressure vessel made of SA 533 B steel in a simulated LWR environment under monotonic rising load (of slow strain rate test) and constant loading was simulated by the combination of FEM stress-strain analysis on a growing crack and dissolution model. From the simulation results, the quantitative relationship between crack tip strain rate and crack propagation rate was discussed. Crack growth rate can be evaluated in terms both of crack tip strain rate and of crack tip solution chemistry such as sulfur concentration and Iss.
| Original language | English |
|---|---|
| Pages (from-to) | 2573-2580 |
| Number of pages | 8 |
| Journal | Transactions of the Japan Society of Mechanical Engineers Series A |
| Volume | 60 |
| Issue number | 579 |
| DOIs | |
| Publication status | Published - 1994 |
Keywords
- Crack Propagation
- Crack Tip Strain Rate
- Film Rupture Strain
- Finite Element Method
- Numerical Analysis
- Stress Corrosion Cracking
ASJC Scopus subject areas
- Materials Science(all)
- Mechanics of Materials
- Mechanical Engineering