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Master Logic Diagram: An Approach to Identify Initiating Events of HTGRs
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Master Logic Diagram: An Approach to Identify Initiating Events of HTGRs (2018)Master Logic Diagram: An Approach to Iden…Application of dynamic probabilistic risk assessment techniques for uncertainty quantification in generation IV reactors (2014)Application of dynamic probab…Fuzzy Failure Rate for Nuclear Power Plant Probabilistic Safety Assessment by Fault Tree Analysis (2012)Fuzzy Failure Rate for Nuclea…Fuzzy uncertainty modeling applied to AP1000 nuclear power plant LOCA (2011)Fuzzy uncertainty modeling ap…Development of Probabilistic Safety Assessment with respect to the first demonstration nuclear power plant of high temperature gas cooled reactor in China (2011)Development of Probabilistic …Master Logic Diagram: method for hazard and initiating event identification in process plants (2003)Master Logic Diagram: method …Identifying and quantifying a complete set of full-power initiating events during early design stages of high-temperature gas-cooled reactors (2023)Identifying and quantifying a…Dynamic generation of accident progression event trees (2008)Development of a code-agnostic computational infrastructure for the dynamic generation of accident progression event trees (2009)A survey of dynamic methodologies for probabilistic safety assessment of nuclear power plants (2012)Dynamic event tree analysis with the SAS4A/SASSYS-1 safety analysis code (2018)Availability assessment of a nuclear reactor limitation system by a Timed Petri Net (2022)Operability Studies and Hazard Analysis (1974)Probabilistic safety analysis in chemical installations (1992)Intelligent systems for HAZOP analysis of complex process plants (2000)Technical modeling in integrated risk assessment of chemical installations (2002)Risk assessment of a compound feed process based on HAZOP analysis and linguistic terms (2016)A novel methodology to measure safety level of a process plant using a system theory based method (STAMP) (2020)Fault Tree Handbook (1987)Fuzzy fault-tree analysis using failure possibility (1993)A historical overview of probabilistic risk assessment development and its use in the nuclear power industry: a tribute to the late Professor Norman Carl Rasmussen (2004)The implementation of fault tree analysis approaches in nuclear power plant probabilistic safety assessment (2019)Safety Analysis Technique for System with Limited Data: Case Study of the Multipurpose Research Reactor in Indonesia (2020)Fuzzy probability and α‐cut based‐fault tree analysis approach to evaluate the reliability and safety of complex engineering systems (2022)On The Quantitative Definition of Risk (1981)Risk and Safety Analysis of Nuclear Systems (2011)Classification Scheme for Root Cause and Failure Modes and Effects Analysis (FMEA) of Passenger Vehicle Recalls (2020)Fuzzy sets (1965)Fuzzy sets (1996)Estimation of failure probability of oil and gas transmission pipelines by fuzzy fault tree analysis (2005)AN INTELLIGENT SYSTEM BY FUZZY RELIABILITY ALGORITHM IN FAULT TREE ANALYSIS FOR NUCLEAR POWER PLANT PROBABILISTIC SAFETY ASSESSMENT (2014)Reliability Study of the AP1000 Passive Safety System by Fuzzy Approach (2014)Risk Assessment of Oxygen Lance Burning Loss Using Bow-Tie Analysis Based on Fuzzy Theory (2020)A plant operating state analysis method in probabilistic safety assessment for multi-unit nuclear power plant (2022)Risk-informed design of advanced nuclear reactor: A target unavailability approach (2023)Probabilistic safety and reliability studies toward licensing and deploying HTGR technology in the Polish chemical industry (2024)
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References

  • 2003Master Logic Diagram: method for hazard and initiating event identification in process plants47 cited
  • 2011Fuzzy uncertainty modeling applied to AP1000 nuclear power plant LOCA20 cited
  • 2011Development of Probabilistic Safety Assessment with respect to the first demonstration nuclear power plant of high temperature gas cooled reactor in China19 cited
  • 2014Application of dynamic probabilistic risk assessment techniques for uncertainty quantification in generation IV reactors15 cited
  • 2012Fuzzy Failure Rate for Nuclear Power Plant Probabilistic Safety Assessment by Fault Tree Analysis9 cited

Cited by

  • 2023Identifying and quantifying a complete set of full-power initiating events during early design stages of high-temperature gas-cooled reactors5 cited

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