TY - GEN
T1 - Crack growth simulation using iterative crack-Tip modeling technique
AU - Lee, Gi Bum
AU - Huh, Nam Su
AU - Jang, Youn Young
AU - Park, Sung Hoon
AU - Park, Noh Hwan
AU - Park, Jun
AU - Park, Kyoungsoo
N1 - Publisher Copyright:
© 2022 American Society of Mechanical Engineers (ASME). All rights reserved.
PY - 2022
Y1 - 2022
N2 - Because of the long-Term operation of nuclear power plants, the assessment of crack growth in pipelines has become one of the most important issues. Crack growth resistance in operating nuclear power plants is typically evaluated using linear elastic fracture mechanics based on ASME B&PV Section XI. However, the ASME method predicts the results conservatively, for complex shapes and conditions, while the finite element analysis, which is more accurate, consumes a substantial amount of time and cost. In this study, a finite element analysis-based iterative crack growth program was created to evaluate cracks with more accuracy and time efficiency. The verification of the program was carried out in two cases. By comparing the produced program with the test result of the three-point bending of the beam with rivet holes, it was shown that the program simulates crack propagation in the right direction. In addition, by comparing the results of the fatigue crack growth (FCG) test of CCT/SENT specimens, it was shown that the program can be applied to the evaluation of major failure mechanisms in the nuclear power plants such as stress corrosion crack (SCC) growth and FCG.
AB - Because of the long-Term operation of nuclear power plants, the assessment of crack growth in pipelines has become one of the most important issues. Crack growth resistance in operating nuclear power plants is typically evaluated using linear elastic fracture mechanics based on ASME B&PV Section XI. However, the ASME method predicts the results conservatively, for complex shapes and conditions, while the finite element analysis, which is more accurate, consumes a substantial amount of time and cost. In this study, a finite element analysis-based iterative crack growth program was created to evaluate cracks with more accuracy and time efficiency. The verification of the program was carried out in two cases. By comparing the produced program with the test result of the three-point bending of the beam with rivet holes, it was shown that the program simulates crack propagation in the right direction. In addition, by comparing the results of the fatigue crack growth (FCG) test of CCT/SENT specimens, it was shown that the program can be applied to the evaluation of major failure mechanisms in the nuclear power plants such as stress corrosion crack (SCC) growth and FCG.
KW - Crack propagation
KW - Fatigue crack growth
KW - J-integral
KW - Stress intensity factor
UR - https://www.scopus.com/pages/publications/85142432107
U2 - 10.1115/PVP2022-84684
DO - 10.1115/PVP2022-84684
M3 - Conference contribution
AN - SCOPUS:85142432107
T3 - American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
BT - Materials and Fabrication
PB - American Society of Mechanical Engineers (ASME)
T2 - ASME 2022 Pressure Vessels and Piping Conference, PVP 2022
Y2 - 17 July 2022 through 22 July 2022
ER -