Evaluation of effectiveness of fault-tolerant techniques in a digital instrumentation and control system with a fault injection experiment

  • Kim, Man Cheol; 
  • Seo, Jeongil; 
  • Jung, Wondea; 
  • Choi, Jong Gyun; 
  • Kang, Hyun Gook; 
  • 외 1명
Citations

WEB OF SCIENCE

8
Citations

SCOPUS

11

초록

Recently, instrumentation and control (I&C) systems in nuclear power plants have undergone digitalization. Owing to the unique characteristics of digital I&C systems, the reliability analysis of digital systems has become an important element of probabilistic safety assessment (PSA). In a reliability analysis of digital systems, fault-tolerant techniques and their effectiveness must be considered. A fault injection experiment was performed on a safety-critical digital I&C system developed for nuclear power plants to evaluate the effectiveness of fault-tolerant techniques implemented in the target system. A software-implemented fault injection in which faults were injected into the memory area was used based on the assumption that all faults in the target system will be reflected in the faults in the memory. To reduce the number of required fault injection experiments, the memory assigned to the target software was analyzed. In addition, to observe the effect of the fault detection coverage of fault-tolerant techniques, a PSA model was developed. The analysis of the experimental result also can be used to identify weak points of fault-tolerant techniques for capability improvement of fault-tolerant techniques. (C) 2018 Korean Nuclear Society, Published by Elsevier Korea LLC.

키워드

Digital I&C system; Probabilistic safety assessment; Fault injection; Fault-tolerant technique; Fault detection coverage; DETECTION COVERAGE; QUANTIFICATION
제목
Evaluation of effectiveness of fault-tolerant techniques in a digital instrumentation and control system with a fault injection experiment
저자
Kim, Man Cheol; Seo, Jeongil; Jung, Wondea; Choi, Jong Gyun; Kang, Hyun Gook; Lee, Seung Jun
DOI
10.1016/j.net.2018.11.012
발행일
2019-06
유형
Article
저널명
Nuclear Engineering and Technology
권
51
호
3
페이지
692 ~ 701

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