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Evaluation Measures About Software V&V of the Safety Digital I&C System in Nuclear Power Plant

  • Peng-Fei GuEmail author
  • Zhe-Ming Liu
  • Hui-Hui Liang
  • Wei-Hua Chen
  • Feng Gao
Conference paper
Part of the Lecture Notes in Electrical Engineering book series (LNEE, volume 455)

Abstract

Since the digital technology is used in the safety system of nuclear power plant (NPP), its safety and reliability are the most important factors to the safety operation of NPP. Software V&V (verification and validation) is a significant method to ensure the safety and reliability of the nuclear power safety I&C (instruments and control) system software, the system to evaluate the efficient of V&V activities needs to further research. An evaluation model of V&V activities has been described in the paper. The anomaly density, V&V effectiveness and V&V efficiency which are to measure the V&V effort, have been included in the model. In the article, the critical point of the anomaly density, V&V effectiveness, and V&V efficiency have been analyzed. Based on the V&V results of nuclear power safety I&C system software, a practice case has been performed to evaluate the V&V activities.

Keywords

NPP Software V&V Evaluation measures I&C 

References

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    Gu, P.F., Xi, W., Chen, W.H., et al.: Evaluation system of software concept V&V about the safety digital I&C system in nuclear power plant. Lecture Notes in Electrical Engineering (2016)Google Scholar

Copyright information

© Springer Nature Singapore Pte Ltd. 2018

Authors and Affiliations

  • Peng-Fei Gu
    • 1
    Email author
  • Zhe-Ming Liu
    • 2
  • Hui-Hui Liang
    • 1
  • Wei-Hua Chen
    • 1
  • Feng Gao
    • 1
  1. 1.State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, Laboratory of I&C Equipment Qualification and Software V&VChina Nuclear Power Design CO., LTD.ShenzhenChina
  2. 2.Product Information Committee of China Instrument and Control SocietyBeijingChina

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