Early quantification of reliability for a safety critical and control system: a case study of reactor core cooling system

  • Authors

    • Vinay Kumar
    • Suraj Gupta
    • Anil Kumar Tripathi
    2018-04-03
    https://doi.org/10.14419/ijet.v7i2.12.11291
  • Fault Tree, Nuclear Power Plan, Reliability Analysis Technique, Reliability Block Diagram, Safety Critical and Control System.

  • Using Probabilistic Reliability analysis for Quantifying reliability of a system is already a common practice in Reliability Engineering community. This method plays an important role in analyzing reliability of nuclear plants and its various components. In Nuclear Power Plants Reactor Core Cooling System is a component of prime importance as its breakdown can disrupt Cooling System of power plant. In this paper, we present a framework for early quantification of Reliability and illustrated with a Safety Critical and Control System as case study which runs in a Nuclear Power Plant.

     

     

  • References

    1. [1] 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, (2017), pp. 38-47.

      [2] 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.

      [3] 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.

      [4] 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.

      [5] ÄŒepin Marko, "Reliability block diagram." In Assessment of Power System Reliability, Springer London, (2011), pp. 119-123.

      [6] Kim M. C., "Reliability block diagram with general gates and its application to system reliability analysis." Annals of Nuclear Energy 38, no. 11, (2011), pp. 2456-2461.

      [7] Lin Cheng-Min, Teng Hui-Kang, Yang Cheng-Chih, Weng Hwei-Li, Chung Ming-Cheng, and Chung Chiu-Chiao, "A mesh network reliability analysis using reliability block diagram," In Industrial Informatics (INDIN), 8th IEEE International Conference, (2010) , pp. 975-979.

      [8] Ericson Clifton A., "Fault tree analysis." In System Safety Conference, Orlando, Florida, (1999), pp. 1-9.

      [9] Wang Bing, Tian Guangdong, Liang Yanping, Qiang Tiangang. "Reliability modeling and evaluation of electric vehicle motor by using fault tree and extended stochastic Petri nets," Journal of Applied Mathematics, Volume 2014, (2014), pp. 1-9.

      [10] Ireson William Gran, Coombs Clyde F., and Moss Richard Y. Handbook of reliability engineering and management. McGraw-Hill Professional, (1996).

      [11] Raiyan Asif, Das Subir, and Islam M. Rafiqul. "Event Tree Analysis of Marine Accidents in Bangladesh." Procedia Engineering 194, (2017), pp. 276-283.

      [12] Singh, Lalit Kumar,Vinod Gopika, and Tripathi Anil Kumar. "Early prediction of software reliability: A case study with a nuclear power plant system." Computer 49, no. 1, (2016), pp. 52-58.

  • Downloads

  • How to Cite

    Kumar, V., Gupta, S., & Kumar Tripathi, A. (2018). Early quantification of reliability for a safety critical and control system: a case study of reactor core cooling system. International Journal of Engineering & Technology, 7(2.12), 248-252. https://doi.org/10.14419/ijet.v7i2.12.11291