Determination of the seismic fragility curve of the containment in pressurized water reactors by considering different failure modes

Document Type : Original Article

Authors

1 - PhD student, of International Institute of Earthquake Engineering and Seismology(IIEES)

2 Assistant Professor of Nuclear and Safety Center, Nuclear Science and Technology Research Institute(NSTRI). Atomic Energy Organization of Iran.

3 Graduated from Master of Civil Engineering, Faculty of Engineering, Islamic Azad University of Tabriz

Abstract

The containment structure of nuclear reactors is the most crucial barrier to releasing radioactive materials into the environment and protecting the reactor against external hazards such as earthquakes and floods. After the Fukushima nuclear accident, the safety of this structure in the earthquake has received much attention. Iran is also located in a region with high and very high seismic hazards and is essential. In this study, the seismic fragility curve of the containment structure of pressurized water reactors used in Bushehr has been determined by considering different failure modes. For this purpose, a computer model simulated in ABAQUS software and incremental dynamic analysis (IDA) have been used. The finite element model has been validated using a lumped mass model. Different failure modes are defined in terms of critical stresses in concrete, rebar, tendons, and steel plate attached to the containment body. Critical points of containment have been identified in terms of these failures. Concrete materials fail at a lower acceleration than other materials. At peak ground accelerations of less than 0.2 g, concrete remains elastic, and no cracks are formed; however, at peak ground accelerations of 2.2 g to 2.75 g, concrete cracks of more than 2 mm form, which allow the release of radioactive materials into the environment. The parameters of fragility, median acceleration capacity, and logarithmic standard deviation of median acceleration capacity were determined to be 2.251 and 0.155, respectively.

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  • Vamvatsikos, D. and C. Cornell, Incremental dynamic analysis, (2002). Earthquakes Engineering and Structural Dynamics, 31
  • Pisharady, A. S., & Basu, P. C. (2010). Methods to derive seismic fragility of NPP components: A summary. Nuclear Engineering and Design, 240(11), 3878–3887. doi:10.1016/j.nucengdes.2010.08.002
  • Huang, Y.-N., Whittaker, A. S., & Luco, N. (2011). A probabilistic seismic risk assessment procedure for nuclear power plants: (I) Methodology. Nuclear Engineering and Design, 241(9)
  • TY - JOUR AU  - Duan, An AU  - Zhao, Zuozhou AU  - Chen, Ju AU  - Qian, Jia-Ru AU  - Jin, Wei PY  “Nonlinear time history analysis of a pre-stressed concrete containment vessel model under Japan's March 11 earthquake” VL  - 13 DO  - 10.12989/cac.2014.13.1.001 JO  - Computers and Concrete ER         
  • Mandal, T.K., S. Ghosh, and N.N. Pujari. (2016). Seismic fragility analysis of a typical Indian PHWR containment: comparison of fragility models: Structural Safety, 11-19.
  • Zhou, L., et al. (2018). Fragility comparison analysis of CPR1000 PWR containment subjected to internal pressure. Nuclear Engineering and Design, 250-264.
  • Jin, S., et al. (2020). A simplified fragility analysis methodology for containment structure subjected to overpressure condition. International Journal of Pressure Vessels and Piping, 104.
  • Jin, S. and J. Gong. (2020). Damage performance based seismic capacity and fragility analysis of existing concrete containment structure subjected to near fault ground motions. Nuclear Engineering and Design. 360-378.
  • Kim, S.-W., et al. (2019). Seismic fragility evaluation of the base-isolated nuclear power plant piping system using the failure criterion based on stress-strain. Nuclear Engineering and Technology. 561-572.
  • Saouma, V.E. and M.A. Hariri-Ardebili (2019). Seismic capacity and fragility analysis of an ASR-affected nuclear containment vessel structure. Nuclear Engineering and Design. 140-156.
  • Zhao, C., N. Yu, and Y. Mo. (2020). Seismic fragility analysis of AP1000 SB considering fluid-structure interaction effects. in Structures -
  • Nguyen, D.-D., et al. (2021). Efficiency of various structural modeling schemes on evaluating seismic performance and fragility of APR1400 containment building. Nuclear Engineering and Technology.
  • Bentaïb, A., H. Bonneville, and G. Cénérino. (2021). Behaviour of Containment Buildings, in Nuclear Power Reactor Core Melt Accidents. 301-336.
  • Bangash, Y. (1983). Containment vessel design and practice. Progress in Nuclear Energy. 107-181.
  • Choun, Y. S., & Park, H. K. (2015). Containment performance evaluation of prestressed concrete containment vessels with fiber reinforcement. Nuclear Engineering and Technology, 47(7), 884-894.
  • Engineers, A.S.o.C. (2021). Seismic design criteria for structures, systems, and components in nuclear facilities. American Society of Civil Engineers.
  • Ghafory-Ashtiany, M., A. Azarbakht, and M. Mousavi. (2012). State of the art: Structure‐specific strong ground motion selection by emphasizing on spectral shape indicators. Proceedings of the 15th World Conference on Earthquake Engineering.
  • Baker, J.W. and C. Allin Cornell. (2006). Spectral shape, epsilon and record selection. Earthquake Engineering & Structural Dynamics. 1077-1095.
  • Wang, G., et al. (2015). Design ground motion library: an interactive tool for selecting earthquake ground motions. Earthquake Spectra. 617-635.
  • Ghafory‐Ashtiany, M., M. Mousavi, and A. Azarbakht. (2011). Strong ground motion record selection for the reliable prediction of the mean seismic collapse capacity of a structure group. Earthquake Engineering & Structural Dynamics. 691-708.
  • Baker, J.W. (2015). Efficient analytical fragility function fitting using dynamic structural analysis. Earthquake Spectra. 57
  • Lin, F., & Tang, H. (2017). Nuclear containment structure subjected to commercial aircraft crash and subsequent vibrations and fire. Nuclear Engineering and Design, 322, 68-80.
  • Liu, J., Kong, J., & Kong, X. (2016). Shaking table model tests of concrete containment vessel (CCV) for CPR1000 nuclear power plant. Progress in Nuclear Energy, 93, 186-204.