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Reliability modeling of safety-critical network communication in a digitalized nuclear power plant

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  • Lee, Sang Hun
  • Kim, Hee Eun
  • Son, Kwang Seop
  • Shin, Sung Min
  • Lee, Seung Jun
  • Kang, Hyun Gook

Abstract

The Engineered Safety Feature-Component Control System (ESF-CCS), which uses a network communication system for the transmission of safety-critical information from group controllers (GCs) to loop controllers (LCs), was recently developed. However, the ESF-CCS has not been applied to nuclear power plants (NPPs) because the network communication failure risk in the ESF-CCS has yet to be fully quantified. Therefore, this study was performed to identify the potential hazardous states for network communication between GCs and LCs and to develop quantification schemes for various network failure causes. To estimate the risk effects of network communication failures in the ESF-CCS, a fault-tree model of an ESF-CCS signal failure in the containment spray actuation signal condition was developed for the case study. Based on a specified range of periodic inspection periods for network modules and the baseline probability of software failure, a sensitivity study was conducted to analyze the risk effect of network failure between GCs and LCs on ESF-CCS signal failure. This study is expected to provide insight into the development of a fault-tree model for network failures in digital I&C systems and the quantification of the risk effects of network failures for safety-critical information transmission in NPPs.

Suggested Citation

  • Lee, Sang Hun & Kim, Hee Eun & Son, Kwang Seop & Shin, Sung Min & Lee, Seung Jun & Kang, Hyun Gook, 2015. "Reliability modeling of safety-critical network communication in a digitalized nuclear power plant," Reliability Engineering and System Safety, Elsevier, vol. 144(C), pages 285-295.
    • Handle: RePEc:eee:reensy:v:144:y:2015:i:c:p:285-295
    DOI: 10.1016/j.ress.2015.07.029
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    References listed on IDEAS

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    1. Koo, Seo Ryong & Seong, Poong Hyun, 2006. "Software design specification and analysis technique (SDSAT) for the development of safety-critical systems based on a programmable logic controller (PLC)," Reliability Engineering and System Safety, Elsevier, vol. 91(6), pages 648-664.
    2. Kang, Hyun Gook & Jang, Seung-Cheol, 2006. "Application of condition-based HRA method for a manual actuation of the safety features in a nuclear power Plant," Reliability Engineering and System Safety, Elsevier, vol. 91(6), pages 627-633.
    3. Kim, Man Cheol & Smidts, Carol S., 2015. "Three suggestions on the definition of terms for the safety and reliability analysis of digital systems," Reliability Engineering and System Safety, Elsevier, vol. 135(C), pages 81-91.
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    Cited by:

    1. Shin, Sung-Min & Lee, Sang Hun & Shin, Seung Ki, 2022. "A novel approach for quantitative importance analysis of safety DI&C systems in the nuclear field," Reliability Engineering and System Safety, Elsevier, vol. 228(C).

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