Abstract
The impact analysis of digital safety-critical systems, the digital plant protection system and the digital engineered safety feature actuation system, on plant risk is embodied and illustrated based on the digital systems’ fault-tree models combined with a typical PSA model of a Korean Standard Nuclear Power Plant. This paper presents the sensitivity study results which used three variables: human failure probability, software failure probability and watchdog timer coverage. The result quantitatively shows that plant risk largely depends on these variables.
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References
H.G. Kang and T. Sung, An analysis of safety-critical digital systems for risk-informed design, Reliability Engineering and Systems Safety, Vol. 78, 2002.
S.H. Han, et al., “PC Workstation-Based Level 1 PRA Code Package KIRAP,” Reliability Engineering and Systems Safety, Vol.30, pp.313–322, 1990
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© 2004 Springer-Verlag London
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Kang, H.G., Jang, SC., Ha, J. (2004). The Risk Effect Analysis of the Digital Safety-Critical Systems in a Nuclear Power Plant. In: Spitzer, C., Schmocker, U., Dang, V.N. (eds) Probabilistic Safety Assessment and Management. Springer, London. https://doi.org/10.1007/978-0-85729-410-4_108
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DOI: https://doi.org/10.1007/978-0-85729-410-4_108
Publisher Name: Springer, London
Print ISBN: 978-1-4471-1057-6
Online ISBN: 978-0-85729-410-4
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