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Seismic Capacity Test of Nuclear Piping System using Multi-platform Shake Table

다지점 진동대를 이용한 원자력발전소 배관계통의 내진성능실험

  • 정진환 (부산대학교 사회환경시스템공학부) ;
  • 계만수 (MIDAS IT 중국지사) ;
  • 서영득 (부산대학교 사회환경시스템공학부) ;
  • 최형석 (부산대학교 지진방재연구센터) ;
  • 김민규 (한국원자력연구원)
  • Received : 2012.07.13
  • Accepted : 2012.12.20
  • Published : 2013.01.02

Abstract

In this study, dynamic characteristics and seismic capacity of the nuclear power plant piping system are evaluated by model test results using multi-platform shake table. The model is 21.2 m long and consists of straight pipes, elbows, and reducers. The stainless steel pipe diameters are 60.3 mm (2 in.) and 88.9 mm (3 in.) and the system was assembled in accordance with ASME code criteria. The dynamic characteristics such as natural frequency, damping and acceleration responses of the piping system were estimated using the measured acceleration, displacement and strain data. The natural frequencies of the specimen were not changed significantly before and after the testing and the failure and leakage of the piping system was not observed until the final excitation. The damping ratio was estimated in the range of 3.13 ~ 4.98 % and it is found that the allowable stress(345 MPa) according to ASME criteria is 2.5 times larger than the measured maximum stress (138 MPa) of the piping system even under the maximum excitation level of this test.

Keywords

References

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