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An integrated modeling approach for event sequence development in multi-unit probabilistic risk assessment

Author

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  • Zhang, Sai
  • Tong, Jiejuan
  • Zhao, Jun

Abstract

To obtain a complete site risk profile for multi-unit nuclear power plants (NPPs), the existing single-unit probabilistic risk assessment (PRA) model needs to be upgraded to address both intra-unit and inter-unit dependencies. The high temperature gas cooled reactor-pebble bed module (HTR-PM), with two reactor-steam generator modules and one shared steam turbine-generator set, is a ready-in-hand pilot for multi-unit PRA (MUPRA) studies. In this paper, a general framework for MUPRA is firstly developed based on HTR-PM PRA methodology. An Integrated Modeling (IM) approach is then proposed for multi-unit event sequence modeling. The approach is discussed in detail and illustrated with a loss of offsite power (LOOP) case study. Also, the limitations of the current analysis are put forward for open discussion.

Suggested Citation

  • Zhang, Sai & Tong, Jiejuan & Zhao, Jun, 2016. "An integrated modeling approach for event sequence development in multi-unit probabilistic risk assessment," Reliability Engineering and System Safety, Elsevier, vol. 155(C), pages 147-159.
    • Handle: RePEc:eee:reensy:v:155:y:2016:i:c:p:147-159
    DOI: 10.1016/j.ress.2016.07.008
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    Citations

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    Cited by:

    1. Jang, Seunghyun & Kim, Yongjin & Jae, Moosung, 2021. "A site risk assessment for internal events: A case study," Reliability Engineering and System Safety, Elsevier, vol. 215(C).
    2. Park, Jong Woo & Lee, Seung Jun, 2022. "Simulation optimization framework for dynamic probabilistic safety assessment," Reliability Engineering and System Safety, Elsevier, vol. 220(C).
    3. Jang, Seunghyun & Jae, Moosung, 2020. "A development of methodology for assessing the inter-unit common cause failure in multi-unit PSA model," Reliability Engineering and System Safety, Elsevier, vol. 203(C).
    4. Kim, Dong-San & Park, Jin Hee & Lim, Ho-Gon, 2020. "A pragmatic approach to modeling common cause failures in multi-unit PSA for nuclear power plant sites with a large number of units," Reliability Engineering and System Safety, Elsevier, vol. 195(C).
    5. Wu, Hui & Li, Yan-Fu & Bérenguer, Christophe, 2020. "Optimal inspection and maintenance for a repairable k-out-of-n: G warm standby system," Reliability Engineering and System Safety, Elsevier, vol. 193(C).
    6. Arigi, Awwal Mohammed & Park, Gayoung & Kim, Jonghyun, 2020. "Dependency analysis method for human failure events in multi-unit probabilistic safety assessments," Reliability Engineering and System Safety, Elsevier, vol. 203(C).
    7. Zhou, Taotao & Modarres, Mohammad & Droguett, Enrique López, 2021. "Multi-unit nuclear power plant probabilistic risk assessment: A comprehensive survey," Reliability Engineering and System Safety, Elsevier, vol. 213(C).
    8. Le Duy, Tu Duong & Vasseur, Dominique, 2018. "A practical methodology for modeling and estimation of common cause failure parameters in multi-unit nuclear PSA model," Reliability Engineering and System Safety, Elsevier, vol. 170(C), pages 159-174.
    9. Yoo, Heejong & Heo, Gyunyoung, 2023. "Analysis of site operating state contributions for multi-unit PSA with Korean NPP Sites," Reliability Engineering and System Safety, Elsevier, vol. 236(C).
    10. Mandelli, D. & Parisi, C. & Alfonsi, A. & Maljovec, D. & Boring, R. & Ewing, S. & St Germain, S. & Smith, C. & Rabiti, C. & Rasmussen, M., 2019. "Multi-unit dynamic PRA," Reliability Engineering and System Safety, Elsevier, vol. 185(C), pages 303-317.
    11. Zhang, Sai & Du, Mengyu & Tong, Jiejuan & Li, Yan-Fu, 2019. "Multi-objective optimization of maintenance program in multi-unit nuclear power plant sites," Reliability Engineering and System Safety, Elsevier, vol. 188(C), pages 532-548.

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