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

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Nuclear Power Plants: Innovative Technologies for Instrumentation and Control Systems (SICPNPP 2017)

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.

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References

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Correspondence to Peng-Fei Gu .

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Gu, PF., Liu, ZM., Liang, HH., Chen, WH., Gao, F. (2018). Evaluation Measures About Software V&V of the Safety Digital I&C System in Nuclear Power Plant. In: Xu, Y., Gao, F., Chen, W., Liu, Z., Gu, P. (eds) Nuclear Power Plants: Innovative Technologies for Instrumentation and Control Systems. SICPNPP 2017. Lecture Notes in Electrical Engineering, vol 455. Springer, Singapore. https://doi.org/10.1007/978-981-10-7416-5_28

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  • DOI: https://doi.org/10.1007/978-981-10-7416-5_28

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  • Publisher Name: Springer, Singapore

  • Print ISBN: 978-981-10-7415-8

  • Online ISBN: 978-981-10-7416-5

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