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The Fault Tolerant Evaluation Model due to the Periodic Automatic Fault Detection Function of the Safety-critical I&C Systems in the Nuclear Power Plants

원전 안전필수 계측제어시스템의 주기적 자동고장검출기능에 따른 고장허용 평가모델

  • Hur, Seop (I&C/HF Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Dong-Hoon (I&C/HF Research Division, Korea Atomic Energy Research Institute) ;
  • Choi, Jong-Gyun (I&C/HF Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Chang-Hwoi (I&C/HF Research Division, Korea Atomic Energy Research Institute) ;
  • Lee, Dong-Young (I&C/HF Research Division, Korea Atomic Energy Research Institute)
  • Received : 2013.04.29
  • Accepted : 2013.06.05
  • Published : 2013.07.01

Abstract

This study suggests a generalized availability and safety evaluation model to evaluate the influences to the system's fault tolerant capabilities depending on automatic fault detection function such as the automatic periodic testings. The conventional evaluation model of automatic fault detection function deals only with the self diagnostics, and supposes that the fault detection coverage of self diagnostics is always constant. But all of the fault detection methods could be degraded. For example, the periodic surveillance test has the potential human errors or test equipment errors, the self diagnostics has the potential degradation of built-in logics, and the automatic periodic testing has the potential degradation of automatic test facilities. The suggested evaluation models have incorporated the loss or erroneous behaviors of the automatic fault detection methods. The availability and the safety of each module of the safety grade platform have been evaluated as they were applied the automatic periodic test methodology and the fault tolerant evaluation models. The availability and safety of the safety grade platform were improved when applied the automatic periodic testing. Especially the fault tolerant capability of the processor module with a weak self-diagnostics and the process parameter input modules were dramatically improved compared to the conventional cases. In addition, as a result of the safety evaluation of the digital reactor protection system, the system safety of the digital parts was improved about 4 times compared to the conventional cases.

Keywords

References

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  1. Risk assessment of safety data link and network communication in digital safety feature control system of nuclear power plant vol.108, 2017, https://doi.org/10.1016/j.anucene.2017.04.025