TY - JOUR
T1 - Simulation of stress corrosion cracking behavior in a tube-shaped specimen of nickel-based alloy 600
AU - Sato, Yasumoto
AU - Watanabe, Kimio
AU - Shoji, Tetsuo
N1 - Funding Information:
This work is partially supported by the Grant-in Aid for the 21st Century COE Program, “The Exploration of the Frontiers of Mechanical Science Based on Nanotechnology” from the Ministry of Education, Culture, Sports, Science and Technology, and is also partially supported by the program of SAT: Study of Safe-Related Advanced Technology from the Japan Nuclear Energy Safety Organization.
PY - 2008/1
Y1 - 2008/1
N2 - Stress corrosion cracking (SCC) simulation code has been developed for the evaluation of SCC behavior in specimens in the shape of field components. The code utilizes numerical calculation of stress/strain states at a crack tip using finite element methods and a formula describing the crack tip reaction kinetics containing unknown environmental parameters. The applicability of this simulation code was investigated by applying the code to the evaluation of SCC behavior in a mock-up of a bottom mounted instrumentation tube for a pressurized water reactor subjected to complex stress/strain states. The results indicate that crack growth rate in a component suffering from certain environments can be estimated using the developed SCC simulation code with pre-determined unknown parameters, using the experimental crack growth rate data measured on other specimens in the same environment.
AB - Stress corrosion cracking (SCC) simulation code has been developed for the evaluation of SCC behavior in specimens in the shape of field components. The code utilizes numerical calculation of stress/strain states at a crack tip using finite element methods and a formula describing the crack tip reaction kinetics containing unknown environmental parameters. The applicability of this simulation code was investigated by applying the code to the evaluation of SCC behavior in a mock-up of a bottom mounted instrumentation tube for a pressurized water reactor subjected to complex stress/strain states. The results indicate that crack growth rate in a component suffering from certain environments can be estimated using the developed SCC simulation code with pre-determined unknown parameters, using the experimental crack growth rate data measured on other specimens in the same environment.
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U2 - 10.1016/j.nucengdes.2007.06.009
DO - 10.1016/j.nucengdes.2007.06.009
M3 - Article
AN - SCOPUS:37749028805
VL - 238
SP - 1
EP - 7
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
SN - 0029-5493
IS - 1
ER -