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Technical reliability of active fire protection features – generic database derived from German nuclear power plants

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  • Forell, Burkhard
  • Peschke, Jörg
  • Einarsson, Svante
  • Röwekamp, Marina

Abstract

For Probabilistic Fire Safety Analysis fire event and fault trees specific to the conditions of the nuclear power plant need to be established to estimate the corresponding branch point probabilities and end states for core damage frequency. That also requires applying technical and human reliability data for fire specific event sequences. The technical reliability of fire detection systems, fire and smoke extraction dampers, fire doors and fire extinguishing systems and equipment including extinguishing media supplies has been estimated by means of their failure rates. To account for epistemic uncertainties Bayesian estimation methods have been used, depending on homogeneity of the studied components.

Suggested Citation

  • Forell, Burkhard & Peschke, Jörg & Einarsson, Svante & Röwekamp, Marina, 2016. "Technical reliability of active fire protection features – generic database derived from German nuclear power plants," Reliability Engineering and System Safety, Elsevier, vol. 145(C), pages 277-286.
    • Handle: RePEc:eee:reensy:v:145:y:2016:i:c:p:277-286
    DOI: 10.1016/j.ress.2015.09.010
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    References listed on IDEAS

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    1. Stephen C. Hora & Ronald L. Iman, 1990. "Bayesian Modeling of Initiating Event Frequencies at Nuclear Power Plants," Risk Analysis, John Wiley & Sons, vol. 10(1), pages 103-109, March.
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    Cited by:

    1. Khakzad, Nima, 2021. "Optimal firefighting to prevent domino effects: Methodologies based on dynamic influence diagram and mathematical programming," Reliability Engineering and System Safety, Elsevier, vol. 212(C).

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