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Application of Expanded Event Trees combined with uncertainty analysis methodologies

Author

Listed:
  • Queral, Cesar
  • Fernández-Cosials, Kevin
  • Zugazagoitia, Eneko
  • Paris, Carlos
  • Magan, Javier
  • Mendizabal, Rafael
  • Posada, Jose

Abstract

During the last decades, the safety analysis of nuclear power plants, have been shifting from conservative models and hypotheses to Best Estimate. Within this trend, the different safety analyses can be categorized depending on their associated conservatisms. The approach that includes Expanded Event Trees together with Best Estimate model and conditions plus uncertainty avoiding conservatisms in system availability can be referred as Extended BEPU (EBEPU). In this sense, an Extended BEPU safety analysis relies on Expanded Event Trees and Best Estimate models to study an accidental sequence.

Suggested Citation

  • Queral, Cesar & Fernández-Cosials, Kevin & Zugazagoitia, Eneko & Paris, Carlos & Magan, Javier & Mendizabal, Rafael & Posada, Jose, 2021. "Application of Expanded Event Trees combined with uncertainty analysis methodologies," Reliability Engineering and System Safety, Elsevier, vol. 205(C).
    • Handle: RePEc:eee:reensy:v:205:y:2021:i:c:s0951832020307468
    DOI: 10.1016/j.ress.2020.107246
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    References listed on IDEAS

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    1. Sanchez-Saez, F. & Sánchez, A.I. & Villanueva, J.F. & Carlos, S. & Martorell, S., 2018. "Uncertainty analysis of a large break loss of coolant accident in a pressurized water reactor using non-parametric methods," Reliability Engineering and System Safety, Elsevier, vol. 174(C), pages 19-28.
    2. Martorell, S. & Sánchez-Sáez, F. & Villanueva, J.F. & Carlos, S., 2017. "An extended BEPU approach integrating probabilistic assumptions on the availability of safety systems in deterministic safety analyses," Reliability Engineering and System Safety, Elsevier, vol. 167(C), pages 474-483.
    3. Kim, Inn Seock & Ahn, Sang Kyu & Oh, Kyu Myung, 2010. "Deterministic and risk-informed approaches for safety analysis of advanced reactors: Part II, Risk-informed approaches," Reliability Engineering and System Safety, Elsevier, vol. 95(5), pages 459-468.
    4. Martorell, S. & Martorell, P. & Martón, I. & Sánchez, A.I. & Carlos, S., 2017. "An approach to address probabilistic assumptions on the availability of safety systems for deterministic safety analysis," Reliability Engineering and System Safety, Elsevier, vol. 160(C), pages 136-150.
    5. Jamali, Kamiar, 2010. "Use of risk measures in design and licensing of future reactors," Reliability Engineering and System Safety, Elsevier, vol. 95(9), pages 935-943.
    6. Kyu Ahn, Sang & Kim, Inn Seock & Myung Oh, Kyu, 2010. "Deterministic and risk-informed approaches for safety analysis of advanced reactors: Part I, deterministic approaches," Reliability Engineering and System Safety, Elsevier, vol. 95(5), pages 451-458.
    7. Ibánez, L. & Hortal, J. & Queral, C. & Gómez-Magán, J. & Sánchez-Perea, M. & Fernández, I. & Meléndez, E. & Expósito, A. & Izquierdo, J.M. & Gil, J. & Marrao, H. & Villalba-Jabonero, E., 2016. "Application of the Integrated Safety Assessment methodology to safety margins. Dynamic Event Trees, Damage Domains and Risk Assessment," Reliability Engineering and System Safety, Elsevier, vol. 147(C), pages 170-193.
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    Cited by:

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    3. Mazgaj, Piotr & Darnowski, Piotr & Kaszko, Aleksej & Hortal, Javier & Dusic, Milorad & Mendizábal, Rafael & Pelayo, Fernando, 2022. "Demonstration of the E-BEPU methodology for SL-LOCA in a Gen-III PWR reactor," Reliability Engineering and System Safety, Elsevier, vol. 226(C).

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