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Dynamic event trees without success criteria for full spectrum LOCA sequences applying the integrated safety assessment (ISA) methodology

Author

Listed:
  • Queral, C.
  • Gómez-Magán, J.
  • París, C.
  • Rivas-Lewicky, J.
  • Sánchez-Perea, M.
  • Gil, J.
  • Mula, J.
  • Meléndez, E.
  • Hortal, J.
  • Izquierdo, J.M.
  • Fernández, I.

Abstract

The integrated safety assessment (ISA) methodology, developed by the Spanish nuclear safety council (CSN), has been applied to the analysis of full spectrum loss of coolant accident (FSLOCA) sequences in a 3-loop pressurized water reactor (PWR). The ISA methodology proposal starts from the unfolding of the dynamic event tree (DET), focusing on the uncertainty of a reduced set of sequence parameters. Outcomes from this step allow assessing the sequence delineation of standard probabilistic safety analysis (PSA) results. For some sequences of interest of the outlined DET, the following ISA methodology steps involve the identification of the damage domain (DD). This is the region of main uncertain parameters space where a safety limit is exceeded during a given sequence. This analysis illustrates the application of this concept, based on transient simulations using MAAP. From the information obtained from the DDs, and considering the time-density probability distributions of human actions and stochastic phenomena occurrence, ISA integrates the dynamic reliability equations proposed to obtain each sequence contribution to the damage exceedance frequency (DEF). The study is then extended to include the uncertainty of subsidiary parameters and, finally, a comparison between the ISA methodology application to FSLOCA and the classical PSA methodology is established.

Suggested Citation

  • Queral, C. & Gómez-Magán, J. & París, C. & Rivas-Lewicky, J. & Sánchez-Perea, M. & Gil, J. & Mula, J. & Meléndez, E. & Hortal, J. & Izquierdo, J.M. & Fernández, I., 2018. "Dynamic event trees without success criteria for full spectrum LOCA sequences applying the integrated safety assessment (ISA) methodology," Reliability Engineering and System Safety, Elsevier, vol. 171(C), pages 152-168.
    • Handle: RePEc:eee:reensy:v:171:y:2018:i:c:p:152-168
    DOI: 10.1016/j.ress.2017.11.004
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    Cited by:

    1. París, C. & Queral, C. & Mula, J. & Gómez-Magán, J. & Sánchez-Perea, M. & Meléndez, E. & Gil, J., 2019. "Quantitative risk reduction by means of recovery strategies," Reliability Engineering and System Safety, Elsevier, vol. 182(C), pages 13-32.
    2. 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).
    3. Kang, Dong Gu, 2020. "Comparison of statistical methods and deterministic sensitivity studies for investigation on the influence of uncertainty parameters: Application to LBLOCA," Reliability Engineering and System Safety, Elsevier, vol. 203(C).
    4. Park, Jong Woo & Lee, Seung Jun, 2022. "Simulation optimization framework for dynamic probabilistic safety assessment," Reliability Engineering and System Safety, Elsevier, vol. 220(C).
    5. Reyes-Fuentes, Melisa & del-Valle-Gallegos, Edmundo & Duran-Gonzalez, Julian & Ortíz-Villafuerte, Javier & Castillo-Durán, Rogelio & Gómez-Torres, Armando & Queral, Cesar, 2021. "AZTUSIA: A new application software for Uncertainty and Sensitivity analysis for nuclear reactors," Reliability Engineering and System Safety, Elsevier, vol. 209(C).
    6. Huang, Jia & You, Jian-Xin & Liu, Hu-Chen & Song, Ming-Shun, 2020. "Failure mode and effect analysis improvement: A systematic literature review and future research agenda," Reliability Engineering and System Safety, Elsevier, vol. 199(C).
    7. Cho, Jaehyun & Lee, Sang Hun & Bang, Young Suk & Lee, Suwon & Park, Soo Yong, 2022. "Exhaustive simulation approach for severe accident risk in nuclear power plants: OPR-1000 full-power internal events," Reliability Engineering and System Safety, Elsevier, vol. 225(C).

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