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Seismic fragility evaluation of the base-isolated nuclear power plant piping system using the failure criterion based on stress-strain

  • Kim, Sung-Wan (Seismic Research and Test Center, Pusan National University) ;
  • Jeon, Bub-Gyu (Seismic Research and Test Center, Pusan National University) ;
  • Hahm, Dae-Gi (Integrated Safety Assessment Division, Korea Atomic Energy Research Institute) ;
  • Kim, Min-Kyu (Integrated Safety Assessment Division, Korea Atomic Energy Research Institute)
  • 투고 : 2018.08.29
  • 심사 : 2018.10.08
  • 발행 : 2019.04.25

초록

In the design criterion for the nuclear power plant piping system, the limit state of the piping against an earthquake is assumed to be plastic collapse. The failure of a common piping system, however, means the leakage caused by the cracks. Therefore, for the seismic fragility analysis of a nuclear power plant, a method capable of quantitatively expressing the failure of an actual piping system is required. In this study, it was conducted to propose a quantitative failure criterion for piping system, which is required for the seismic fragility analysis of nuclear power plants against critical accidents. The in-plane cyclic loading test was conducted to propose a quantitative failure criterion for steel pipe elbows in the nuclear power plant piping system. Nonlinear analysis was conducted using a finite element model, and the results were compared with the test results to verify the effectiveness of the finite element model. The collapse load point derived from the experiment and analysis results and the damage index based on the stress-strain relationship were defined as failure criteria, and seismic fragility analysis was conducted for the piping system of the BNL (Brookhaven National Laboratory) - NRC (Nuclear Regulatory Commission) benchmark model.

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참고문헌

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