Network reliability analysis of digital instrument and control system with GO-FLOW methodology

Abstract

In this paper, the network reliability of an actual digital instrument and control system (DICS) network is analyzed by using GO-FLOW methodology (GFM). The evaluations of common-cause failure (CCF) and uncertainty are incorporated. Three significant CCF groups (real time servers, gateways, reactor protection system) and three typical time intervals (10 min, 1 h, and 24 h) are selected in the analysis. It is concluded that the network contribution of CCF accounts for over 68% of the system failure probability. The result indicates that GFM is suitable for the network reliability analysis.

Keywords

GO-FLOW methodology / common-cause failure / network / digital instrument and control system

References

[1] Lee Jae Min, Park Tae Rim, Kim Hyung Seok et al. A communication network with high safety, maintainability, and user convenience for digital I and C systems of nuclear power plants[C]. In: 8th IEEE International Conference on Emerging Technologies and Factory Automation. Antibes-Juan les Pins, France, 2001. 353–358.

[2] Xing Liudong. An efficient binary-decision-diagram-based approach for network reliability and sensitivity analysis [J]. IEEE Transactions on Systems, Man, and Cybernetics-Part A: System and Humans, 2008, 38(1): 105-115.

[3] Cancela H., El Khadiri M. A recursive variance-reduction algorithm for estimating communication-network reliability[J]. IEEE Transactions on Reliability, 1995, 44(4): 592-602.

[4] Han W., Zhang S., Sun Yu. Research on and evaluation of the reliability of a communication network management and control system[J]. Journal of Xidian University, 2008, 35(1): 133-139.

[5] Sieteng S., Rai S. An efficient cutset approach for evaluating communication-network reliability with heterogeneous link-capacities [J]. IEEE Transactions on Reliability, 2005, 54(1): 133-144.

[6] Matsuoka T., Michiyuki K. GO-FLOW: A new reliability analysis methodology [J]. Nuclear Science and Engineering, 1988, 98(1): 64-78.

[7] Matsuoka T., Michiyuki K. The GO-FLOW reliability analysis methodology — Analysis of common cause failures with uncertainty [J]. Nuclear Engineering and Design, 1997, 175(3): 205-214.

[8] Huang T., Cai Q., Zhao X., et al. Application of GOFLOW methodology to RHS reliability analysis in PWR [J]. Nuclear Power Engineering, 2009, 30(4): 55-58.

[9] Shang Y., Chen L., Cai Q., et al. Analysis of continuously maintained complex redundancy system with CCF based on GO-FLOW methodology[J]. Nuclear Power Engineering, 2009, 30(6): 70-75.

[10] Lin J., Yan Z., Gong S., et al. GO-FLOW methodology and improved exact algorithm [J]. Systems Engineering and Electronics, 2005, 27(1): 193-196.

[11] Shang Y., Cai Q., Chen L., et al. Uncertainty analysis of failure probability for nuclear reactor coolant pumps group system based on GO-FLOW methodology [J]. Nuclear Power Engineering, 2010, 31(5): 118-123.

[12] Qiu Z., Xie R., Zou Yifeng. Application of GOFLOW in the risk analysis on vegetable logistics safety [J]. Journal of Wuhan University of Technology (Transportation Science and Engineering), 2010, 34(2): 332-336.