Dynamic Fault Tree (DFT) has drawn attention from comprehensive industrial systems in recent years. Many analytical approaches are developed to analyze DFT, such as Markov Chain based method, Inclusion-Exclusion Rule based method, and Sum-of-Disjoint-Product theory based method. Novel methods such as Bayesian Network and Petri Net are also used to solve DFT. However, Basic events are usually assumed unrepairable and are restricted to specific probabilistic distributions. And some methods may suffer from combination explosion. This paper applies Dynamic Uncertain Causality Graph (DUCG) to analyze DFT to overcome the aforementioned issues. DUCG is a newly proposed Probabilistic Graphic Model for large complex industrial systems which allows for dynamics, uncertainties and logic cycles. The DUCG based methodology can be summarized as event mapping, logical mapping, and numerical mapping. This paper studies how to map the PAND, FDEP, SEQ AND SPARE sequential logic gates into equivalent representations in DUCG. With the DUCG representation mode, one can analyze DFT with algorithms in DUCG. Future work will be done on benchmark tests and on software development.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5144-9
PROCEEDINGS PAPER
Dynamic Fault Tree Analysis Based on Dynamic Uncertain Causality Graph
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
Search for other works by this author on:
Zhenxu Zhou
Tsinghua University, Beijing, China
Chunling Dong
Tsinghua University, Beijing, China
Qin Zhang
Tsinghua University, Beijing, China
Paper No:
ICONE26-81636, V002T14A010; 8 pages
Published Online:
October 24, 2018
Citation
Zhou, Z, Dong, C, & Zhang, Q. "Dynamic Fault Tree Analysis Based on Dynamic Uncertain Causality Graph." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management. London, England. July 22–26, 2018. V002T14A010. ASME. https://doi.org/10.1115/ICONE26-81636
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