Control Improvement of the Reactor Protection System

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In this paper an optimal maintenance policy for a Reactor Protection System (RPS) for a nuclear plant was developed. RPS consists of continuously operating sub-systems that were subject to random failures. A block system diagram for RPS had been proposed that facilitates analyzing of individual sub-systems separately. The proposed maintenance policy is the Age Replacement model, which incorporated both corrective and preventive maintenances. A Markov model was used to optimize the preventive maintenance interval of those sub-systems whose failure and repair rates were exponentially distributed. Finally, a sensitivity analysis had been performed and recommendations for maintaining the required RPS availability have been suggested.

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4199-4202

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July 2011

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© 2011 Trans Tech Publications Ltd. All Rights Reserved

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[1] S.S. Lee, D.J. Yoon, J.H. Lee and S. Lee. Reliability analysis of the reactor protection system with fault diagnosis. Key Engineering Materials, 2004, 270-273.

DOI: 10.4028/www.scientific.net/kem.270-273.1749

Google Scholar

[2] J.H. Bickel. Risk implications of digital reactor protection system operating experience. Reliability Engineering and System Safety, 2008, 93: 107-124.

DOI: 10.1016/j.ress.2006.10.015

Google Scholar

[3] M. Khalaquzzaman, H.G. Kang, M.C. Kim and P.H. Seong. Optimization of periodic testing frequency of a reactor protection system based on a risk-cost model and public risk perception. Nuclear Engineering and Design, 2011, 241(5): 1538-1547.

DOI: 10.1016/j.nucengdes.2011.02.003

Google Scholar

[4] P. Pyy. An analysis of maintenance failures at nuclear power plant. Reliability Engineering and System Safety, 2001, 72: 293-302.

DOI: 10.1016/s0951-8320(01)00026-6

Google Scholar

[5] D.Y. Lee, J.G. Choi and J. Lyou. A safety assessment methodology for a digital reactor protection system. International Journal of Control Automation and Systems, 2006, 4 (1): 105-112.

Google Scholar