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Multi-unit nuclear power plant probabilistic risk assessment: A comprehensive survey

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  • Zhou, Taotao
  • Modarres, Mohammad
  • Droguett, Enrique López

Abstract

A growing concern regarding probabilistic risk assessments (PRA) is the impact of dependencies among reactor units co-located at a nuclear power site, especially after the March 2011 Fukushima Daiichi accident. To address these dependencies and identify the critical contributors to the entire site risk, multi-unit probabilistic risk assessment (MUPRA) has been actively developed by various research and regulatory agencies. However, possible inter-unit dependencies in MUPRA have led to some technical issues and challenges associated with the development and modeling of initiating events, accident sequences, end states, and risk metrics relevant to multi-unit sites. This paper provides a comprehensive survey and assessment of the state of current knowledge in MUPRA. The critical recent literature is synthesized and discussed, focusing on three facets: multi-unit event characterization, MUPRA methodological development, and site-based risk metrics and risk aggregation. This survey aims to identify the key issues addressed and challenges faced by the research and development activities of MUPRA, and identifies gaps and opportunities for future research and developments.

Suggested Citation

  • 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).
    • Handle: RePEc:eee:reensy:v:213:y:2021:i:c:s0951832021003070
    DOI: 10.1016/j.ress.2021.107782
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    References listed on IDEAS

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    1. Zhou, Taotao & Modarres, Mohammad & Droguett, Enrique López, 2019. "Multi-unit risk aggregation with consideration of uncertainty and bias in risk metrics," Reliability Engineering and System Safety, Elsevier, vol. 188(C), pages 473-482.
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    6. Liu, Jiaxin & Yu, Deping & Yang, Taibo & Liu, Caixue & Wang, Guangjin & Liu, Xiaoming, 2023. "Discovering the causes for the change of the vibration characteristics of the core support barrel in PWR nuclear power plants: A combined investigation based on ex-core neutron noise analysis and nume," Reliability Engineering and System Safety, Elsevier, vol. 234(C).
    7. 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).
    8. Sejin Baek & Gyunyoung Heo, 2021. "Application of Dynamic Fault Tree Analysis to Prioritize Electric Power Systems in Nuclear Power Plants," Energies, MDPI, vol. 14(14), pages 1-17, July.
    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. Alanen, Jarmo & Linnosmaa, Joonas & Malm, Timo & Papakonstantinou, Nikolaos & Ahonen, Toni & Heikkilä, Eetu & Tiusanen, Risto, 2022. "Hybrid ontology for safety, security, and dependability risk assessments and Security Threat Analysis (STA) method for industrial control systems," Reliability Engineering and System Safety, Elsevier, vol. 220(C).
    11. Zhao, Yan-Gang & Qin, Miao-Jun & Lu, Zhao-Hui & Zhang, Long-Wen, 2021. "Seismic fragility analysis of nuclear power plants considering structural parameter uncertainty," Reliability Engineering and System Safety, Elsevier, vol. 216(C).
    12. Lilli, Giordano & Sanavia, Matteo & Oboe, Roberto & Vianello, Chiara & Manzolaro, Mattia & De Ruvo, Pasquale Luca & Andrighetto, Alberto, 2024. "A semi-quantitative risk assessment of remote handling operations on the SPES Front-End based on HAZOP-LOPA," Reliability Engineering and System Safety, Elsevier, vol. 241(C).
    13. Wanxin Feng & Ming Wang & Zhixin Xu & Yu Yu, 2023. "The Method of Calculating the Frequency of the Initiating Event in a Dual-Unit Site with the Example of LOOP Events," Energies, MDPI, vol. 16(2), pages 1-8, January.
    14. 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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