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Probabilistic analysis of containment structural performance in severe accidents

Author

Listed:
  • Seyed Mojtaba Hoseyni

    (Building and Housing Research Center)

  • Seyed Mohsen Hoseyni

    (Islamic Azad University)

  • Faramarz Yousefpour

    (Nuclear Science and Technology Research Center)

  • Kaveh Karimi

    (Islamic Azad University)

Abstract

To study the capacity of reactor containment under pressurization, it is important to know the way that this structure reacts under internal pressure loading. This is usually performed through structural fragility analysis for assuring that the containment structure has high capability of withstanding the loads associated with severe accident phenomena and its consequent pressurization, therefore the potential for significant radioactive release is small. In this paper, the methodology of structural fragility analysis for pressurization is thoroughly reviewed, and its practical application is demonstrated on a real case Pressurized Water Reactor containment. The reactor containment is analyzed using finite element method, and the ultimate pressure is computed. Containment performance is further analyzed using the structural fragility method. The structural fragility serves as the interface between the structural analysis model and the risk model of the systems. Therefore, a probabilistic scheme is used to represent the structural fragility. Final outcome of this study is the overpressure fragility curve which depicts the probability of failure of the containment at a given value of pressure. This curve is a key element in conducting probabilistic safety assessment (level 2 PSA) of nuclear power plants.

Suggested Citation

  • Seyed Mojtaba Hoseyni & Seyed Mohsen Hoseyni & Faramarz Yousefpour & Kaveh Karimi, 2017. "Probabilistic analysis of containment structural performance in severe accidents," International Journal of System Assurance Engineering and Management, Springer;The Society for Reliability, Engineering Quality and Operations Management (SREQOM),India, and Division of Operation and Maintenance, Lulea University of Technology, Sweden, vol. 8(3), pages 625-634, September.
    • Handle: RePEc:spr:ijsaem:v:8:y:2017:i:3:d:10.1007_s13198-016-0540-1
    DOI: 10.1007/s13198-016-0540-1
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    Cited by:

    1. Zheng, Zhi & Tian, Aonan & Pan, Xiaolan & Ji, Duofa & Wang, Yong, 2024. "The damage-based fragility analysis and probabilistic safety assessment of containment under internal pressure," Reliability Engineering and System Safety, Elsevier, vol. 241(C).
    2. Jin, Song & Gong, Jinxin, 2021. "Fragility analysis and probabilistic performance evaluation of nuclear containment structure subjected to internal pressure," Reliability Engineering and System Safety, Elsevier, vol. 208(C).

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