Probabilistic safety assessment (PSA) of a safety critical system: a case study of a nuclear power plant

Authors

  • Vinay Kumar

  • Dewanshu Pratihar

  • Anil Kumar Tripathi

Received date: April 8, 2018

Accepted date: April 8, 2018

Published date: April 3, 2018

DOI:

https://doi.org/10.14419/ijet.v7i2.12.11281

Keywords:

Common Cause Failure (CCF), Nuclear Power Plant (NPP), Probabilistic Safety Assessment (PSA), Safety Critical System.

Abstract

Probabilistic Safety Assessment approach has been successfully applied in engineering, economics, computer science and statistics to re-solve a wide range of safety-related problems. However, using Probabilistic Safety Assessment for quantifying safety of a safety critical system is a challenging task in Safety Engineering community. This method plays an essential role in analyzing safety of safety critical sys-tems and its various components. Therefore, in this paper, we present Probabilistic Safety Assessment framework which can be used to quantify the critical failures of a systems. The approach is well demonstrated on a Digital Feed Water Control System uses in a Nuclear Power Plant as safety critical system.

 

References

  1. [1] Wong W. Eric, Debroy Vidroha, and Restrepo Andrew, "The role of software in recent catastrophic accidents," IEEE Reliability Society 2009 Annual Technology Report, (2009), pp. 1-8,

    [2] Sunanda B. Esther, Seetharamaiah P., "Modeling of Safety Critical Systems Using Petri Nets," ACM SIGSOFT Software Engineering Notes 40, no. 1, (2015), pp. 1-7.

    [3] Lawrence J. Dennis, Software reliability and safety in nuclear reactor protection systems. Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission, (1993).

    [4] Goseva-Popstojanova Katerina, and Trivedi Kishor S., "Failure correlation in software reliability models," IEEE Transactions on Reliability 49, no. 1, (2000), pp. 37-48.

    [5] Chu T. L., Martinez-Guridi G., Lehner J., and Overland D. Issues Associated with Probabilistic Failure Modeling Of Digital Systems. No. Bnl--72381-2004-Cp. Brookhaven National Laboratory, (2004).

    [6] Chu T. L., Martinez-Guridi G., Yue M., and Lehner J. A Review of Software-Induced Failure Experience. No. Bnl--Nureg-77124-2006-Cp. Brookhaven National Laboratory, (2006).

    [7] Chu T. L., Martinez-Guridi G., Yue M., Lehner J., and Samanta P. "Traditional Probabilistic Risk Assessment Methods for Digital Systems (NUREG/CR-6962)." US NRC, (2008).

    [8] Yue Meng, and Chu Tsong-Lun. "Estimation of Failure Rates of Digital Components Using a Hierarchical Bayesian Method (PSAM-0320)." In Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM). ASME Press, (2006).

    [9] Kumar Vinay, Singh Lalit Kumar, Tripathi Anil Kumar, and Singh Pooja. "Safety Analysis of Safety Critical Systems Using State-Space Models." IEEE Software 34, no. 4, pp. 38-47, 2017.

    [10] Kumar Vinay, Singh Lalit Kumar, and Tripathi Anil Kumar. "Transformation of deterministic models into state space models for safety analysis of safety critical systems: A case study of NPP." Annals of Nuclear Energy 105, (2017), pp. 133-143.

    [11] Kumar Vinay, Singh Lalit, and Tripathi A. K. "A Probabilistic Hazard Assessment Framework for Safety Critical and Control Systems: A Case Study for a Nuclear Power Plant." Nuclear Technology 197, no. 1, (2017), pp. 20-28.

    [12] Kumar Vinay, Singh Lalit, and Tripathi Anil. "Reliability Analysis of safety critical and control systems: A state-of-the-art review." IET Software (online), (2017), pp. 1-18.

    [13] Chu T. L., Yue M., Martinez-Guridi G., Mernick K., Lehner J., and Kuritzky A. "Modeling a Digital Feedwater Control System Using Traditional Probabilistic Methods." Washington DC: US Nuclear Regulatory Commission, (2009).

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How to Cite

Kumar, V., Pratihar, D., & Kumar Tripathi, A. (2018). Probabilistic safety assessment (PSA) of a safety critical system: a case study of a nuclear power plant. International Journal of Engineering and Technology, 7(2.12), 210-213. https://doi.org/10.14419/ijet.v7i2.12.11281

Received date: April 8, 2018

Accepted date: April 8, 2018

Published date: April 3, 2018