Journal of the Korean Society for Precision Engineering (한국정밀공학회지)

Korean Society for Precision Engineering (한국정밀공학회)
권호 표지

Dynamic Analysis and Structural Safety Evaluation of the Cabinet of a Reactor Safety System

원자로 보호계통 캐비닛의 동해석과 구조 안전성 평가

  • 이부윤 (계명대학교 기계자동차공학부) ;
  • 조정래 (계명대학교 대학원 기계공학과) ;
  • 김원진 (계명대학교 기계자동차공학부) ;
  • 정동관 (두산중공업(주) 기술연구원) ;
  • 손재율 (씨아이이에스대구(주))
  • Published : 2005.12.01
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Abstract

Responses of the cabinet of the reactor safety system under seismic leadings are analyzed, its dynamic characteristics and structural reliability being evaluated. Analyzed natural frequencies are compared with those measured from a resonance test. Structural safety of the cabinet is evaluated in consideration of the required response spectrums of the operation-base and safe-shutdown earthquakes. Transient responses of the cabinet are analyzed with input ground acceleration measured during the seismic test, accelerations being extracted at the locations of the main internal parts. The transient responses are compared with those from the seismic test, favorable results being shown.

Keywords

References

  1. Regulatory Guide 1.60, 'Design Response Spectra for Seismic design of Nuclear Power plants,' U.S. Atomic Energy Commission, 1973
  2. Regulatory Guide 1.61, 'Damping Values for Seismic Design of Nuclear Power Plants,' U.S. Atomic Energy Commission, 1973
  3. Regulatory Guide 1.92, 'Combination of Modes and Spatial Components in Seismic Response Analysis,' U.S. Atomic Energy Commission, 1974
  4. Regulatory Guide 1.29, 'Seismic Design Classification,' U.S. Nuclear Regulatory Commission, 1978
  5. Regulatory Guide 1.222, 'Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components,' U.S. Nuclear Regulatory Commission, 1978
  6. Regulatory Guide 1.100, 'Seismic Qualification of Electric and mechanical Equipment for Nuclear Power Plants,' U.S. Nuclear Regulatory Commission, 1988
  7. ANSI/IEEE SID 344-1987, 'IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations,' The Institute of Electrical and Electronics Engineers Inc, 1987
  8. The Enforcement Ordinance of Law of Atomic Energy, 1997
  9. Lee, J. K., Kim, J. Y., Chung, P. J. and Chung, J. H., 'Seismic Qualification of the Air Conditioning Equipment for Nuclear Power Plant,' Journal of KSNVE, Vol. 9, No.3, pp. 535-543, 1999
  10. Yang, B. S. and Kim, Y. H., 'Seismic Response Analysis of Steam Turbine-Gnerator Rotor System(1st Report, In Case of Rotor-Bearing System only),' Journal of KSNVE, Vol. 9, No.3, pp. 554-564, 1999
  11. Byeon, H. S. and Lee, J. K., 'Seismic Qualification of the Main Control Board for Nuclear Power Plant,' Journal of KSNVE, Vol. 12, No. 11, pp. 856-863, 2002 https://doi.org/10.5050/KSNVN.2002.12.11.856
  12. Lee, J. K., Kim, J. Y. and Rhee, H. N., 'Seismic Qualification of the Air Cleaning Units for Nuclear Power Plants Ulchin 5&6,' Transactions of the KSME A, Vol. 26, No.7, pp. 1376-1383, 2002
  13. Lee, J. H. and Chang, S. H., 'Improvement of Pressurizer PROV System through Micro-Computer and PRA,' Journal of the Korean Nuclear Society, Vol. 17, No.4, pp. 302-317, 1985
  14. Auh, G. S., Hwang, D. H. and Kim, S. H., 'A Steady-State Margin Comparison between Analog and Digital Protection Systems,' Journal of the Korean Nuclear Society, Vol. 22, No.1, pp. 45-58, 1990
  15. Mok, J. I. and Seong, P. H., 'Optimal Inspection Periods of Safety System of Wolsung Nuclear Power Plant Unit I with Human Error Consideration,' Journal of the Korean Nuclear Society, Vol. 26, No.1, pp. 9-19, 1994
  16. Joe, Y. H. and Park, H. G., 'Modal Testing of Seismic Monitoring System Cabinet of Nuclear Power Plant,' Journal of the Korean Society of Civil Engineers, Vol. 19, No.2, pp. 449-457, 1999
  17. ANSYS, 'User's Manual,' Revision 6.2, ANSYS Inc., 2002