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Sensitivity analysis on the effect of software-induced common cause failure probability in the computer-based reactor trip system unavailability
6 references·4 citing·41 second hop
Sensitivity analysis on the effect of software-induced common cause failure probability in the computer-based reactor trip system unavailability (2013)Sensitivity analysis on the effect of sof…Diversity Strategies for Nuclear Power Plant Instrumentation and Control Systems (2010)Diversity Strategies for Nucl…Risk implications of digital reactor protection system operating experience (2006)Risk implications of digital …An analysis of safety-critical digital systems for risk-informed design (2002)An analysis of safety-critica…Recent applications of PSA for managing nuclear power plant safety (2001)Recent applications of PSA fo…An overview of PSA importance measures (2001)An overview of PSA importance…The American society of mechanical engineers (1902)The American society of mecha…The implementation of fault tree analysis approaches in nuclear power plant probabilistic safety assessment (2019)The implementation of fault t…A Novel Weakest t-Norm based Fuzzy Importance Measure for Fuzzy Fault Tree Analysis of Combustion Engineering Reactor Protection System (2019)A Novel Weakest t-Norm based …Common cause failure model updating for risk monitoring in nuclear power plants based on alpha factor model (2017)Common cause failure model up…Sensitivity Study on Availability of I&C Components Using Bayesian Network (2013)Sensitivity Study on Availabi…Guidelines for Safe Automation of Chemical Processes (1993)Computers Take Flight: A History of NASA's Pioneering Digital Fly-by-Wire Project (2000)Process safety management of highly hazardous chemicals (2000)Hazard analysis for identifying common cause failures of digital safety systems using a redundancy-guided systems-theoretic approach (2020)A Redundancy-Guided Approach for the Hazard Analysis of Digital Instrumentation and Control Systems in Advanced Nuclear Power Plants (2021)Reliability and Fault Tree Analysis (1977)Two Measures of Risk Importance and Their Application (1985)Special committee review of the Nuclear Regulatory Commission's severe accident risks report (NUREG--1150) (1990)Probabilistic Safety Assessment for Instrumentation and Control Systems in Nuclear Power Plants: An Overview (2004)Risk monitor riskangel for risk-informed applications in nuclear power plants (2016)Integrated Risk-Informed Design (I-RID) methodological framework and computational application for FLEX equipment storage buildings of Nuclear Power Plants (2019)Reliability and risk analysis (1990)A Benchmark System for Comparing Reliability Modeling Approaches for Digital Instrumentation and Control Systems (2009)AN OVERVIEW OF RISK QUANTIFICATION ISSUES FOR DIGITALIZED NUCLEAR POWER PLANTS USING A STATIC FAULT TREE (2009)Systematic development of scenarios caused by cyber-attack-induced human errors in nuclear power plants (2017)Systems analysis programs for hands-on integrated reliability evaluations (SAPHIRE), Version 5.0 (1995)Bayesian parameter estimation in probabilistic risk assessment (1998)A model for estimation of reactor spurious shutdown rate considering maintenance human errors in reactor protection system of nuclear power plants (2010)Reliability Assessment for a Safety-Related Digital Reactor Protection System Using Event-Tree/Fault-Tree (ET/FT) Method (2020)International survey on PSA figures of merit (1999)Improving the analysis of dependable systems by mapping fault trees into Bayesian networks (2001)RELIABILITY ANALYSIS OF DIGITAL SYSTEMS IN A PROBABILISTIC RISK ANALYSIS FOR NUCLEAR POWER PLANTS (2012)Uncertainties and quantification of common cause failure rates and probabilities for system analyses (2004)A robust Bayesian approach to modeling epistemic uncertainty in common-cause failure models (2013)A general cause based methodology for analysis of common cause and dependent failures in system risk and reliability assessments (2015)Explicit and implicit Bayesian Network-based methods for the risk assessment of systems subject to probabilistic common-cause failures (2020)Review on the Application of Living PSA in Nuclear Power (2024)Fuzzy fault tree analysis: a review of concept and application (2013)An extension to Fuzzy Fault Tree Analysis (FFTA) application in petrochemical process industry (2014)Applications of fuzzy faulty tree analysis and expert elicitation for evaluation of risks in LPG refuelling station (2014)Applications of FFTA–HFACS for Analyzing Human and Organization Factors in Electric Misoperation Accidents (2021)An approach to human reliability in man-machine systems using error possibility (1988)Estimation of failure probability of oil and gas transmission pipelines by fuzzy fault tree analysis (2005)An overview of fault tree analysis and its application in model based dependability analysis (2017)Comparative study of fault tree analysis and 24Model: taking the cause analysis of the Quanzhou Xinjia Hotel collapse accident as an example (2023)Misconceptions of Risk (2009)Accident precursors, near misses, and warning signs: Critical review and formal definitions within the framework of Discrete Event Systems (2013)Evolution of Safety and Security Risk Assessment methodologies towards the use of Bayesian Networks in Process Industries (2021)Visual search, anticipation, and reactive comparisons between highly-skilled and beginning tennis players (1996)How Useful Is Quantitative Risk Assessment? 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this work references cited by second hop

References

  • 1902The American society of mechanical engineers945 cited
  • 2001An overview of PSA importance measures245 cited
  • 2002An analysis of safety-critical digital systems for risk-informed design55 cited
  • 2010Diversity Strategies for Nuclear Power Plant Instrumentation and Control Systems41 cited
  • 2006Risk implications of digital reactor protection system operating experience26 cited
  • 2001Recent applications of PSA for managing nuclear power plant safety25 cited

Cited by

  • 2017Common cause failure model updating for risk monitoring in nuclear power plants based on alpha factor model16 cited
  • 2013Sensitivity Study on Availability of I&C Components Using Bayesian Network12 cited
  • 2019A Novel Weakest t-Norm based Fuzzy Importance Measure for Fuzzy Fault Tree Analysis of Combustion Engineering Reactor Protection System12 cited
  • 2019The implementation of fault tree analysis approaches in nuclear power plant probabilistic safety assessment9 cited

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