SYMPOSIA PAPER Published: 01 January 1992
STP24686S

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)

Source

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.

Author Information

Shoji, T
Research Institute for Fracture Technology, Tohoku University, Aramaki Aoba, Sendai, Japan
Moriya, S
Research Institute for Fracture Technology, Tohoku University, Aramaki Aoba, Sendai, Japan
Yoshida, K
Research Institute for Fracture Technology, Tohoku University, Aramaki Aoba, Sendai, Japan
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Details
Developed by Committee: G01
Pages: 44–66
DOI: 10.1520/STP24686S
ISBN-EB: 978-0-8031-5210-6
ISBN-13: 978-0-8031-1473-9