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Development of Probabilistic Safety Assessment with respect to the first demonstration nuclear power plant of high temperature gas cooled reactor in China
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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 Safety Asses…Probabilistic safety and reliability studies toward licensing and deploying HTGR technology in the Polish chemical industry (2024)Probabilistic safety and reli…Risk-informed design of advanced nuclear reactor: A target unavailability approach (2023)Risk-informed design of advan…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…An event sequence modeling method in multi-unit probabilistic risk assessment for high temperature gas-cooled reactor (2022)An event sequence modeling me…A plant operating state analysis method in probabilistic safety assessment for multi-unit nuclear power plant (2022)A plant operating state analy…Master Logic Diagram: An Approach to Identify Initiating Events of HTGRs (2018)Master Logic Diagram: An Appr…Application of NUREG/CR-6850 to the fire risk quantification of a High Temperature Gas-Cooled Reactor (2018)Application of NUREG/CR-6850 …A Combined Monte Carlo and Possibilistic Approach to Uncertainty Propagation in Event Tree Analysis (2008)Human factors, human reliability and risk assessment in license renewal of a nuclear power plant (2009)Improved Modelling and Assessment of the Performance of Firefighting Means in the Frame of a Fire PSA (2015)A hybrid Monte Carlo and possibilistic approach to estimate non-suppression probability in fire probabilistic safety analysis (2017)Master Logic Diagram: method for hazard and initiating event identification in process plants (2003)Fuzzy uncertainty modeling applied to AP1000 nuclear power plant LOCA (2011)Application of dynamic probabilistic risk assessment techniques for uncertainty quantification in generation IV reactors (2014)Seismic PSA method for multiple nuclear power plants in a site (2006)Multi-unit Level 1 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site (2018)International Atomic Energy Agency (2022)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)An event classification schema for evaluating site risk in a multi-unit nuclear power plant probabilistic risk assessment (2013)Scenario clustering and dynamic probabilistic risk assessment (2013)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)An overview of PSA importance measures (2001)Variance based sensitivity analysis of model output. Design and estimator for the total sensitivity index (2009)Application of dynamic Bayesian network to risk analysis of domino effects in chemical infrastructures (2015)Impact of equipment reliability on safety classification of research reactors (2024)
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Cited by

  • 2024Probabilistic safety and reliability studies toward licensing and deploying HTGR technology in the Polish chemical industry9 cited
  • 2023Risk-informed design of advanced nuclear reactor: A target unavailability approach8 cited
  • 2022A plant operating state analysis method in probabilistic safety assessment for multi-unit nuclear power plant7 cited
  • 2018Application of NUREG/CR-6850 to the fire risk quantification of a High Temperature Gas-Cooled Reactor7 cited
  • 2018Master Logic Diagram: An Approach to Identify Initiating Events of HTGRs6 cited
  • 2022An event sequence modeling method in multi-unit probabilistic risk assessment for high temperature gas-cooled reactor6 cited
  • 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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