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Preliminary Study on Reliability Analysis of Safety I&C System in NPP

  • Chao Guo
  • Duo Li
  • Huasheng Xiong
Part of the Advances in Intelligent and Soft Computing book series (AINSC, volume 144)

Abstract

Digital instrumentation and control (I&C) systems, such as digital Reactor Protection System (RPS), are being employed gradually at newly-built and upgraded Nuclear Power Plants (NPPs). The reliability analysis of digital I&C system turns to be a research focus. This paper proposes a preliminary study on reliability analysis for the digital RPS of High Temperature Gas-Cooled Reactor-Pebble bed Module (HTR-PM). We first introduce the function and structure of RPS in HTR-PM; then the processes of failure mode and effect analysis (FMEA) at system level are given; finally we present the FMEA of a computer device as an example and introduce the future work. This study analyses all possible safety-relevant implications arising from failures in RPS and promotes the reliability analysis of the digital RPS in HTR-PM.

Keywords

nuclear power plant digital reactor protection system reliability failure mode and effect analysis 

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References

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    Li, F., Yang, Z., An, Z., Zhang, L.: The first digital reactor protection system in China. Nuclear Engineering and Design 218, 215–225 (2002)CrossRefGoogle Scholar
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Copyright information

© Springer-Verlag GmbH Berlin Heidelberg 2012

Authors and Affiliations

  1. 1.Institute of Nuclear and New Energy TechnologyTsinghua UniversityBeijingChina

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