본문 바로가기
KERD
논문KCI 등재

Safety analysis of marine nuclear reactor in severe accident with dynamic fault trees based on cut sequence method

2

조회

0

다운로드

0

인용

0

참고문헌

키워드

주제분류원자력공학

초록

Dynamic fault tree (DFT) and its related research methods have received extensive attention in safety analysis and reliability engineering. DFT can perform reliability modelling for systems with sequential correlation, resource sharing, and cold and hot spare parts. A technical modelling method of DFT is proposed for modelling ship collision accidents and loss-of-coolant accidents (LOCAs). Qualitative and quantitative analyses of DFT were carried out using the cutting sequence (CS)/extended cutting sequence (ECS) method. The results show nine types of dynamic fault failure modes in ship collision accidents, describing the fault propagation process of a dynamic system and reflect the dynamic changes of the entire accident system. The probability of a ship collision accident is 2.378  109 by using CS. This failure mode cannot be expressed by a combination of basic events within the same event frame after an LOCA occurs in a marine nuclear reactor because the system contains warm spare parts. Therefore, the probability of losing reactor control was calculated as 8.125  106 using the ECS. Compared with CS, ECS is more efficient considering expression and processing capabilities, and has a significant advantage considering cost.

Abstract

Dynamic fault tree (DFT) and its related research methods have received extensive attention in safety analysis and reliability engineering. DFT can perform reliability modelling for systems with sequential correlation, resource sharing, and cold and hot spare parts. A technical modelling method of DFT is proposed for modelling ship collision accidents and loss-of-coolant accidents (LOCAs). Qualitative and quantitative analyses of DFT were carried out using the cutting sequence (CS)/extended cutting sequence (ECS) method. The results show nine types of dynamic fault failure modes in ship collision accidents, describing the fault propagation process of a dynamic system and reflect the dynamic changes of the entire accident system. The probability of a ship collision accident is 2.378  109 by using CS. This failure mode cannot be expressed by a combination of basic events within the same event frame after an LOCA occurs in a marine nuclear reactor because the system contains warm spare parts. Therefore, the probability of losing reactor control was calculated as 8.125  106 using the ECS. Compared with CS, ECS is more efficient considering expression and processing capabilities, and has a significant advantage considering cost.

참고문헌 (35)

  1. Christophe Bonneuil, "Early warnings and emerging accountability: Total’s responses to global warming, 1971–2021", Global Environmental Change, 71, pp.102386~ (2021), Elsevier BV[DOI]
  2. R. Poudyal, "Mitigating the current energy crisis in Nepal with renewable energy sources", Renewable and Sustainable Energy Reviews, 116, pp.109388~ (2019)
  3. T. Kusunoki, "Design of advanced integral-type marine reactor", MRX. Nuclear Engineering & Design, 201(2-3), pp.155~175 (2000)[DOI]
  4. Yang Sui, "A novel approach for occupational health and safety and environment risk assessment for nuclear power plant construction project", Journal of Cleaner Production, 258, pp.120945~ (2020), Elsevier BV[DOI]
  5. Alexander R. Sich, "The Chernobyl Nuclear Power Plant Unit-4 Accident", Encyclopedia of Nuclear Energy, pp.30~52 (2021), Elsevier[DOI]
  6. M. Leslie, "Amid uncertainty for US nuclear power, three mile Island shuts down", Engineering, 6(1), pp.4~5 (2020)[DOI]
  7. K. Akahane, "The Fukushima nuclear power plant accident and exposures in the environment", Env, 32(2), pp.136~143 (2012)[DOI]
  8. X. Zheng, "Dynamic probabilistic risk assessment of nuclear power plants using multi-fidelity simulations", Reliability Engineering & System Safety, 223, pp.108503~ (2022)
  9. M. Ghadhab, "Safety analysis for vehicle guidance systems with dynamic fault trees", Reliability Engineering & System Safety, 186(6), pp.37~50 (2019)[DOI]
  10. E. Gascard, "Quantitative analysis of dynamic fault trees by means of Monte Carlo simulations : event-driven simulation approach", Reliability Engineering & System Safety, 180(12), pp.487~504 (2018)[DOI]
  11. J. Dehlinger, "Dynamic event", fault tree analysis of multi-agent systems using galileo, 2008, 429~434
  12. G. Merle, "Probabilistic algebraic analysis of fault trees with priority dynamic gates and repeated events", IEEE Transactions on Reliability, 59(1), pp.250~261 (2010)[DOI]
  13. D. Ge, "Quantitative analysis of dynamic fault trees using improved sequential binary decision diagrams", Reliability Engineering &System Safety, 142, pp.289~299 (2015)[DOI]
  14. K. S. Hsueh, "The development and application of the accident dynamic simulator for dynamic probabilistic risk assessment of nuclear power plants", Reliability Engineering & System Safety, 52(3), pp.297~314 (1996)[DOI]
  15. D. R. Karanki, "Discrete dynamic event tree analysis of MLOCA using ADS-TRACE", International Topical Meeting on Probabilistic Safety Assessment and Analysis 2011, PSA 2011, 1, pp.610~622 (2011)
  16. A. Alfonsi, "Dynamic Event Tree Analysis through RAVEN”, ANS PSA 2013International Topical Meeting on Probabilistic Safety Assessment and Analysis", Sepp, 22-26 (2013), American Nuclear Society[DOI]
  17. D. R. Karanki, "Quantification of Dynamic Event Trees e a comparison with event trees for MLOCA scenario", Reliability Engineering & System Safety, 147, pp.19~31 (2016)[DOI]
  18. D. R. Karanki, "A dynamic event tree informed approach to probabilistic accident sequence modeling: dynamics and variabilities in medium LOCA", Reliability Engineering and System Safety, 142, pp.011~ (2015)
  19. M. Amirsoltani, "Development of a dynamic event tree (DET)to analyze SBO accident in VVER-1000", V446 nuclear reactor, 2022, pp.165, 108786~
  20. Tarannom Parhizkar, "Utne, an-Erik Vinnem, Online Probabilistic Risk Assessment of Complex Marine Systems" (2022), Springer
  21. Roshandel R. ParhizkarT, "Long term performance degradation analysis and optimization of anode supported solid oxide fuel cell stacks", Energy Conversion Management, 133, pp.20~30 (2017)[DOI]
  22. R. Roshandel, "Degradation based optimization framework for long term applications of energy systems. case study: solid oxide fuel cell stacks", Energy, 107, pp.172~1816 (2016)[DOI]
  23. T. Parhizkar, "Degradation based operational optimization model to improve the productivity of energy systems. case study : solid oxide fuel cell stacks", Energy Conversion Management, 158, pp.81~91 (2018)
  24. R. Roshandel, "A new approach to optimize the operating conditions of a polymer electrolyte membrane fuel cell based on degradation mechanisms", Energy Systems, 4(3), pp.219~237 (2013)[DOI]
  25. T. Parhizkar, "Handbook of Research on Predictive Modeling and Optimization Methods in Science Andengineering" (2018), IGI Global
  26. T. Parhizkar, "Aging based optimal scheduling framework for power plants using equivalent operating hour approach", Applied Energy, 205, pp.1345~1363 (2017)[DOI]
  27. A. F. Sotoodeh, "Aging based design and operation optimization of organic rankine cycle systems", Energy Conversion Management, 199, pp.111892~ (2019)
  28. C. A. Thieme, "Assessing ship risk model applicability to marine autonomous surface ships", Ocean Engineering, 165, pp.140~154 (2018)[DOI]
  29. Tarannom Parhizkar, "Supervised Dynamic Probabilistic Risk Assessment of Complex Systems, Part 1: General Overview", Reliability Engineering & System Safety, 208, pp.107406~ (2021), Elsevier BV[DOI]
  30. Tarannom Parhizkar, "Supervised dynamic probabilistic risk assessment of complex systems, part 2: Application to risk-informed decision making, practice and results", Reliability Engineering & System Safety, 208, pp.107392~ (2021), Elsevier BV[DOI]
  31. M. Kloos, "MCDET : a probabilistic dynamics method combining Monte Carlo simulation with the discrete dynamic event tree approach", Nuclear Science and Engineering, 153(2), pp.137~156 (2006)[DOI]
  32. A. Hakobyan, "Dynamic generation of accident progression event trees", Nuclear Engineering and Design, 238, pp.3457~3467 (2008)[DOI]
  33. A. Mosleh, "Dynamic PRA Using ADS with RELAP5 Code as its Thermal Hydraulic Module", PSAM, 4, pp.2468~2473 (1998), Springer-Verlag
  34. J. M. Izquierdo, "TRETA : a general purpose simulation code with application on nuclear power plant transients", Journal of the Spanish Nuclear Society, 58, pp.41~47 (1987)

관련 논문AI추천

Zero-suppressed ternary decision diagram algorithm for solving noncoherent fault trees in probabilistic safety assessment of nuclear power plants정우식한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제6호Reliability analysis of nuclear safety-class DCS based on T-S fuzzy fault tree and Bayesian networkDeng Zhiguang, Huang Qichang, Jian Yifan, Ma Quan, Peng Hao, Zhang Xu한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제5호Direct fault-tree modeling of human failure event dependency in probabilistic safety assessment김만철, 김지숙, 한상훈한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제1호Comparison of event tree/fault tree and convolution approaches in calculating station blackout risk in a nuclear power plant김만철한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제1호How to Incorporate Human Failure Event Recovery into Minimal Cut Set Generation Stage for Efficient Probabilistic Safety Assessments of Nuclear Power Plants박성규, 정우식, Jeff Riley, John E. Weglian한국원자력학회 · Nuclear Engineering and Technology2022 · 제54권 제1호On the use of time-dependent success criteria within Risk-Informed Analyses. Application to LONF-ATWS sequences in PWR reactorsParis Carlos, Posada Jose Maria, Queral Cesar, Rebollo Maria Jose, Sanchez-Perea Miguel, Sanchez-Torrijos Jorge한국원자력학회 · Nuclear Engineering and Technology2022 · 제54권 제12호

이 간행물의 다른 논문 (39건)