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A Safety Assessment Methodology for a Digital Reactor Protection System
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A Safety Assessment Methodology for a Digital Reactor Protection System (2006)A Safety Assessment Methodology for a Dig…Handbook of human-reliability analysis with emphasis on nuclear power plant applications. Final report (1983)Handbook of human-reliability…An Overview of Probabilistic Safety Assessment for Nuclear Safety: What Has Been Done, and Where Do We Go from Here? (2024)An Overview of Probabilistic …A new approach for dynamic reliability analysis of reactor protection system for HPR1000 (2023)A new approach for dynamic re…Development of dynamic fault tree model for reactor protection system (2020)Development of dynamic fault …Reliability model of the digital reactor protection system considering the repair time and common cause failure (2017)Reliability model of the digi…Module level reliability performance evaluation of digital reactor protection system considering the repair and common cause failure (2017)Module level reliability perf…Reliability modeling of safety-critical network communication in a digitalized nuclear power plant (2015)Reliability modeling of safet…A model for estimation of reactor spurious shutdown rate considering maintenance human errors in reactor protection system of nuclear power plants (2010)A model for estimation of rea…AN OVERVIEW OF RISK QUANTIFICATION ISSUES FOR DIGITALIZED NUCLEAR POWER PLANTS USING A STATIC FAULT TREE (2009)AN OVERVIEW OF RISK QUANTIFIC…A Quantitative Study on Risk Issues in Safety Feature Control System Design in Digitalized Nuclear Power Plant (2008)A Quantitative Study on Risk …An analysis of safety-critical digital systems for risk-informed design (2002)Probabilistic Safety Assessment and Management (2004)Risk assessment of safety data link and network communication in digital safety feature control system of nuclear power plant (2017)Human reliability for safe and efficient civil infrastructure operation and maintenance – A review (2020)An analysis of maintenance failures at a nuclear power plant (2001)Spurious activation analysis of safety-instrumented systems (2016)A comparison of fault trees and the Dynamic Flowgraph Methodology for the analysis of FPGA-based safety systems part 2: Theoretical investigations (2018)A fast BDD algorithm for large coherent fault trees analysis (2003)A computational method for probabilistic safety assessment of I&C systems and human operators in nuclear power plants (2005)Judgment Under Uncertainty: Heuristics and Biases. (1984)Expert elicitation approach for performing ATHEANA quantification (2003)FAULT DETECTION COVERAGE QUANTIFICATION OF AUTOMATIC TEST FUNCTIONS OF DIGITAL I&C SYSTEM IN NPPS (2012)PSA model with consideration of the effect of fault-tolerant techniques in digital I&C systems (2015)Probabilistic risk assessment modeling of digital instrumentation and control systems using two dynamic methodologies (2010)Reliability assessment of safety instrumented systems subject to different demand modes (2010)International Atomic Energy Agency (2022)Introduction to Monte Carlo simulation (2008)Introduction to Monte Carlo simulation (2009)Galileo: A Tool for Dynamic Fault Tree Analysis (2000)Dynamic fault tree analysis using Monte Carlo simulation in probabilistic safety assessment (2008)An open-source application to model and solve dynamic fault tree of real industrial systems (2011)A knowledge transfer-based method for risk analysis and procedure optimization of emergency schemes (2023)The generalization of Latin hypercube sampling (2015)A fuzzy Bayesian network approach for risk analysis in process industries (2017)Safety analysis of process systems using Fuzzy Bayesian Network (FBN) (2018)A Bayesian Network Inference Approach for Dynamic Risk Assessment Using Multisource-Based Information Fusion in an Interval Type-2 Fuzzy Set Environment (2024)On The Quantitative Definition of Risk (1981)A comprehensive framework for verification, validation, and uncertainty quantification in scientific computing (2011)Stuxnet and the Future of Cyber War (2011)The Concept of Probability in Safety Assessments of Technological Systems (1990)The paradoxes of almost totally safe transportation systems (2001)How Useful Is Quantitative Risk Assessment? (2004)
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References

  • 1983Handbook of human-reliability analysis with emphasis on nuclear power plant applications. Final report1,460 cited

Cited by

  • 2009AN OVERVIEW OF RISK QUANTIFICATION ISSUES FOR DIGITALIZED NUCLEAR POWER PLANTS USING A STATIC FAULT TREE25 cited
  • 2024An Overview of Probabilistic Safety Assessment for Nuclear Safety: What Has Been Done, and Where Do We Go from Here?21 cited
  • 2023A new approach for dynamic reliability analysis of reactor protection system for HPR100021 cited
  • 2015Reliability modeling of safety-critical network communication in a digitalized nuclear power plant20 cited
  • 2010A model for estimation of reactor spurious shutdown rate considering maintenance human errors in reactor protection system of nuclear power plants16 cited
  • 2008A Quantitative Study on Risk Issues in Safety Feature Control System Design in Digitalized Nuclear Power Plant12 cited
  • 2020Development of dynamic fault tree model for reactor protection system12 cited
  • 2017Module level reliability performance evaluation of digital reactor protection system considering the repair and common cause failure11 cited
  • 2017Reliability model of the digital reactor protection system considering the repair time and common cause failure10 cited

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