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Multi-unit dynamic PRA

Author

Listed:
  • Mandelli, D.
  • Parisi, C.
  • Alfonsi, A.
  • Maljovec, D.
  • Boring, R.
  • Ewing, S.
  • St Germain, S.
  • Smith, C.
  • Rabiti, C.
  • Rasmussen, M.

Abstract

Dynamic Probabilistic Risk Analysis (PRA) methods couple stochastic methods (e.g., RAVEN) with safety analysis codes (e.g., RELAP5-3D) to determine risk associated to complex systems such as nuclear plants. Compared to classical PRA methods, which are based on static logic structures (e.g., Event-Trees, Fault-Trees), they can evaluate with higher resolution the safety impact of timing and sequencing of events on the accident progression. Recently, special attention has been given to nuclear plant sites which consist of multiple units and, in particular, on the safety impact of system dependencies, shared systems and common resources on core damage frequencies. In the literature, classical PRA methods have been employed to model multi-unit sites in a limited number of cases while Dynamic PRA methods have never been applied to analyze a full multi-unit model. This paper presents a PRA analysis of a multi-unit plant using Dynamic PRA methods. We employ RAVEN as stochastic tool coupled with RELAP5-3D. The site under consideration consists of three units (each unit is composed by a reactor and its associated spent fuel pool) while the considered initiating event is a seismic induced station blackout event. This paper describes in detail how the multi-unit site has been constructed and, in particular, how unit dependencies and shared resources are modeled from both a deterministic and stochastic point of view.

Suggested Citation

  • 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.
  • Handle: RePEc:eee:reensy:v:185:y:2019:i:c:p:303-317
    DOI: 10.1016/j.ress.2018.12.029
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    References listed on IDEAS

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    1. Marseguerra, M. & Zio, E. & Devooght, J. & Labeau, P.E., 1998. "A concept paper on dynamic reliability via Monte Carlo simulation," Mathematics and Computers in Simulation (MATCOM), Elsevier, vol. 47(2), pages 371-382.
    2. 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.
    3. Modarres, Mohammad & Zhou, Taotao & Massoud, Mahmoud, 2017. "Advances in multi-unit nuclear power plant probabilistic risk assessment," Reliability Engineering and System Safety, Elsevier, vol. 157(C), pages 87-100.
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    Cited by:

    1. Zheng, Xiaoyu & Tamaki, Hitoshi & Sugiyama, Tomoyuki & Maruyama, Yu, 2022. "Dynamic probabilistic risk assessment of nuclear power plants using multi-fidelity simulations," Reliability Engineering and System Safety, Elsevier, vol. 223(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. Al-Douri, Ahmad & Levine, Camille S. & Groth, Katrina M., 2023. "Identifying human failure events (HFEs) for external hazard probabilistic risk assessment," Reliability Engineering and System Safety, Elsevier, vol. 235(C).
    4. 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).
    5. Hu, Yunwei & Parhizkar, Tarannom & Mosleh, Ali, 2022. "Guided simulation for dynamic probabilistic risk assessment of complex systems: Concept, method, and application," Reliability Engineering and System Safety, Elsevier, vol. 217(C).
    6. Maidana, Renan G. & Parhizkar, Tarannom & Gomola, Alojz & Utne, Ingrid B. & Mosleh, Ali, 2023. "Supervised dynamic probabilistic risk assessment: Review and comparison of methods," Reliability Engineering and System Safety, Elsevier, vol. 230(C).
    7. Yoon, Jae Young & Kim, Dong-San, 2022. "Estimating the adverse effects of inter-unit radioactive release on operator actions at a multi-unit site," Reliability Engineering and System Safety, Elsevier, vol. 228(C).

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