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Technical Paper

Semi-Markov Reliability Analysis of Alternating Systems in a Nuclear Power Plant

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Pages 230-241 | Published online: 12 May 2017

References

  • “Technical Specifications - Enhancing the Safety Impact,” NUREG-1024, U.S. Nuclear Regulatory Commission (Nov. 1983).
  • “Technical Specifications Improvement Program,” SECY 88-307, U.S. Nuclear Regulatory Commission (Oct. 1988).
  • W. E. VESELY, “Evaluation of Allowed Outage Times from a Risk and Reliability Standpoint,” NUREG/CR-5425, Science Applications International (Aug. 1989).
  • “Improvements to Technical Specification Surveillance Requirements,” NUREG-1366, U.S. Nuclear Regulatory Commission (Feb. 1990).
  • T. MANKAMO, “Is It Beneficial to Test/Start Up the Remaining Pairs of Standby Safety Systems in a Failure Situation?,” Proc. Int. Topi. Conf. Probabilistic Safety Assessment and Risk Management, Zurich, Switzerland, August 30-September 4, 1987, p. 765, Swiss Nuclear Society and European Nuclear Society (1987).
  • N. Z. CHO et al., “Analysis of Allowed Outage Times at the Byron Generating Station,” NUREG/CR-4404, Brookhaven National Laboratory (June 1986).
  • W. S. JUNG and N. Z. CHO, “Semi-Markov Reliability Analysis of Three Test/Repair Policies for Standby Safety Systems in a Nuclear Power Plant,” Reliab. Eng. and System Safety, 31, 1 (1991).
  • I. A. PAPAZOGLOU and N. Z. CHO, “Review and Assessment of Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System,” BNL-NUREG-51780, Brookhaven National Laboratory (Apr. 1984).
  • R. HOWARD, Dynamic Probabilistic Systems, Vols. I and II, John Wiley and Sons, Inc., New York (1971).
  • S. M. ROSS, Stochastic Process, John Wiley and Sons, New York (1983).

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