Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Development of the structural health record of containment building in nuclear power plant

  • Chu, Shih-Yu (Department of Civil Engineering, National Cheng Kung University) ;
  • Kang, Chan-Jung (Department of Civil Engineering, National Cheng Kung University)
  • Received : 2020.04.21
  • Accepted : 2020.12.16
  • Published : 2021.06.25
Download PDF
⟨ Previous Next ⟩

Abstract

The main objective of this work is to propose a reliable routine standard operation procedures (SOP) for structural health monitoring and diagnosis of nuclear power plants (NPPs). At present, NPPs have monitoring systems that can be used to obtain the quantitative health record of containment (CTMT) buildings through system identification technology. However, because the measurement signals are often interfered with by noise, the identification results may introduce erroneous conclusions if the measured data is directly adopted. Therefore, this paper recommends the SOP for signal screening and the required identification procedures to identify the dynamic characteristics of the CTMT of NPPs. In the SOP, three recommend methods are proposed including the Recursive Least Squares (RLS), the Observer Kalman Filter Identification/Eigensystem Realization Algorithm (OKID/ERA), and the Frequency Response Function (FRF). The identification results can be verified by comparing the results of different methods. Finally, a preliminary CTMT healthy record can be established based on the limited number of earthquake records. It can be served as the quantitative reference to expedite the restart procedure. If the fundamental frequency of the CTMT drops significantly after the Operating Basis Earthquake and Safe Shutdown Earthquake (OBE/SSE), it means that the restart actions suggested by the regulatory guide should be taken in place immediately.

Keywords

Acknowledgement

This research was supported in part by the Atomic Energy Council (AEC) of the Executive Yuan of the Republic of China (Taiwan) under grant NL1080298 and the Ministry of Science and Technology of the Republic of China (Taiwan) under grant MOST 106-2625-M-006-001. These supports are greatly appreciated. The measured records of the KSNPP provided by the Taipower Company of Taiwan is also acknowledged.

References

  1. U.S. Nuclear Regulatory Commission, 10 CFR Part 100 - Reactor Site Criteria, USNRC, 2017.
  2. IAEA, Safety Guide No. NS-G-1.6 - Seismic Design and Qualification for Nuclear Power Plants, International Atomic Energy Agency, 2003.
  3. IAEA, Earthquake Preparedness and Response for Nuclear Power Plants, International Atomic Energy Agency, Vienna,, 2011. Safety Reports Series No. 66.
  4. IAEA, On-line Monitoring for Improving Performance of Nuclear Power Plants, Part 1: Instrument Channel Monitoring, International Atomic Energy Agency, 2008.
  5. IAEA, On-line Monitoring for Improving Performance of Nuclear Power Plants, Part 2: Process and Component Condition Monitoring and Diagnostics, International Atomic Energy Agency, 2008.
  6. Guidelines for Structural Integrity Assessment for Nuclear Power Components Experienced Earthquake, JANTI-SANE-G1, JANTI-SANE-G2, Japan Nuclear Safety Institute, 2012 (in Japanese).
  7. EPRI NP-6695, Guidelines for Nuclear Plant Response to an Earthquake, Electric Power Research Institute, Palo Alto, CA, 1989.
  8. American National Standards Institute (ANSI), ANSI/ANS-2.23, Nuclear Power Plant Response to an Earthquake, American Nuclear Society, IL, USA, 2002.
  9. EPRI Report 30020007220, Guidelines for Nuclear Plant Response to an Earthquake, Electric Power Research Institute, Palo Alto, CA, 2013.
  10. American National Standards Institute (ANSI), ANSI/ANS-2.23-2016, Nuclear Power Plant Response to an Earthquake, American Nuclear Society, IL, USA, 2016.
  11. EPRI Report 3002005284, Guidelines for Nuclear Power Plant Response to an Earthquake, Electric Power Research Institute, Palo Alto, CA, 2015.
  12. USNRC, Pre-earthquake Planning, Shutdown and Restart of a Nuclear Power Plant Following an Earthquake, Office of Nuclear Regulatory Research, 2016. Draft Regulatory Guide DG-1337 (Proposed Revision 1 to Regulatory Guide RG 1.166).
  13. USNRC, Pre-earthquake Planning and Immediate Nuclear Power Plant Operator Post-earthquake Actions, Office of Nuclear Regulatory Research, Regulatory Guide RG 1, 1997, p. 166.
  14. USNRC, Restart of a Nuclear Power Plant Shut Down by a Seismic Event, Office of Nuclear Regulatory Research, Regulatory Guide RG 1, 1997, p. 167.
  15. M.M. Hasan, J.K. Mayaka, J.C. Jung, Development of earthquake instrumentation for shutdown and restart criteria of the nuclear power plant using multivariable decision-making process, Nucl. Eng. Technol. 50 (6) (2018) 860-868, https://doi.org/10.1016/j.net.2018.04.004.
  16. D.-D. Nguyen, B. Thusa, T.-S. Han, T.-H. Lee, Identifying significant earthquake intensity measures for evaluating seismic damage and fragility of nuclear power plant structures, Nucl. Eng. Technol. 52 (1) (2020) 192-205, https://doi.org/10.1016/j.net.2019.06.013.
  17. J. Hur, E. Althoff, H. Sezen, R. Denning, T. Aldemir, Seismic assessment and performance of nonstructural components affected by structural modeling, Nucl. Eng. Technol. 49 (2) (2017) 387-394, https://doi.org/10.1016/j.net.2017.01.004.
  18. F. Lin, H. Li, Safety analysis of nuclear containment vessels subjected to strong earthquakes and subsequent tsunamis, Nucl. Eng. Technol. 49 (5) (2017) 1079-1089, https://doi.org/10.1016/j.net.2017.03.008.
  19. P. Caravani, M.L. Watson, W.T. Thomson, Recursive least-squares time domain identification of structural parameters, J. Appl. Mech., Trans. ASME 44 Ser E (1) (1977) 135-140.
  20. J.N. Juang, Applied System Identification, Prentice Hall, Englewood Cliffs, New Jersey, 1994.
  21. J.W. Lin, R. Betti, A.W. Smyth, R.W. Longman, On-line identification of nonlinear hysteretic structural systems using a variable trace approach, Earthq. Eng. Struct. Dynam. 30 (9) (2001) 1279-1303, https://doi.org/10.1002/eqe.63.
  22. S.Y. Chu, S.C. Lo, Application of real-time adaptive identification technique on damage detection and structural health monitoring, Struct. Contr. Health Monit. 16 (2) (2009) 154-177, https://doi.org/10.1002/stc.304.
  23. S.Y. Chu, S.C. Lo, Application of the on-line recursive least-squares method to perform structural damage assessment, Struct. Contr. Health Monit. 18 (3) (2011) 241-264, https://doi.org/10.1002/stc.362.
  24. P. Varpasuo, System identification of NPP reactor building on the basis of blast test responses, in: SMiRT-15, August 15-20, 1999.
  25. Y. Naito, A. Niousha, Analytical study on system identification of fixed-base transfer functions for an embedded reactor building, in: SMiRT-18,August 7-12, 2005.
  26. A. Niousha, Y. Naito, M. Kan, A. Onouchi, A. Tachibana, System identification of a nuclear reactor building under fixed-base condition using measured data, in: SMiRT-18, August 7-12, 2005.
  27. A. Onouchi, A. Niousha, Y. Naito, M. Kan, Y. Mihara, Forced vibration test of an ABWR nuclear reactor building -Data analysis and system identification, in: SMiRT-18, August 7-12, 2005.
  28. A. Niousha, Y. Naito, E. Miyasaka, S. Uchiyama, Dynamic characteristics of a SC Building in Kashiwazaki NPP site using vibration test - Part 1: data analysis and system identification, in: SMiRT-19,August, 2007.
  29. Atomic Energy Council, Executive Yuan ROC, The Third Ten-Year Integrated Safety Assessment Report of KuoSheng Nuclear Power Plant, NRD-SER-101-12, 2012 (in Chinese).