Failure Modes and Effects Analysis (FMEA) is a useful tool to find possible flaws, to reduce cost and to shorten research cycle in complex industrial systems. Fault Tree Analysis (FTA) has gained credibility over the past years, not only in nuclear industry, but also in other industries like aerospace, petrochemical, and weapon. Both FMEA and FTA are effective techniques in safety analysis, but there are still many uncertain factors in them that are not well addressed until now. This paper combines FMEA and FTA based on Dynamic Uncertain Causality Graph (DUCG) to solve this issue. Firstly, the FMEA model is mapped into a corresponding DUCG graph. Secondly, FTA model is mapped into a corresponding DUCG graph. Thirdly, combine the above DUCG graphs. Finally, users can modify the combined DUCG graph and calculations are made. This paper bridges the gap between FMEA and FTA by combining the two methods using DUCG. And additional modeling power and analytical power can be achieved with the advantages of the combined DUCG safety analysis model and its inference algorithm. This method can also promote the application of DUCG in the system reliability and safety analysis. An example is used to illustrate this method.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5146-3
PROCEEDINGS PAPER
Safety Analysis Model of DUCG Based on FMEA/FTA
Zhenxu Zhou,
Zhenxu Zhou
Tsinghua University, Beijing, China
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Chunling Dong,
Chunling Dong
Tsinghua University, Beijing, China
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Qin Zhang
Qin Zhang
Tsinghua University, Beijing, China
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Zhenxu Zhou
Tsinghua University, Beijing, China
Hao Nie
Tsinghua University, Beijing, China
Chunling Dong
Tsinghua University, Beijing, China
Qin Zhang
Tsinghua University, Beijing, China
Paper No:
ICONE26-81484, V004T06A018; 6 pages
Published Online:
October 24, 2018
Citation
Zhou, Z, Nie, H, Dong, C, & Zhang, Q. "Safety Analysis Model of DUCG Based on FMEA/FTA." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation. London, England. July 22–26, 2018. V004T06A018. ASME. https://doi.org/10.1115/ICONE26-81484
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