Estimating the frequency of cyber threats to nuclear power plants based on operating experience analysis | 0 | 0.34 | 2022 |
Reliability Of The System With Loops: Factor Graph Based Approach | 0 | 0.34 | 2021 |
A statistical approach to estimating effects of performance shaping factors on human error probabilities of soft controls | 10 | 0.81 | 2015 |
Study on Diagnosis Error Assessment of Operators in Nuclear Power Plants. | 0 | 0.34 | 2014 |
A Framework of Human Reliability Analysis Method Considering Soft Control in Digital Main Control Rooms | 0 | 0.34 | 2014 |
Development Of Digital-Device-Based Cooperation Support System To Aid Communication Between Mcr Operators And Field Workers In Nuclear Power Plants (Npps) | 0 | 0.34 | 2014 |
FBDVerifier: Interactive and Visual Analysis of Counterexample in Formal Verification of Function Block Diagram. | 11 | 1.01 | 2010 |
Attentional-Resource Effectiveness Measures in Monitoring and Detection Tasks in Nuclear Power Plants | 0 | 0.34 | 2010 |
SMV model-based safety analysis of software requirements | 0 | 0.34 | 2009 |
A computational model for evaluating the effects of attention, memory, and mental models on situation assessment of nuclear power plant operators | 5 | 0.50 | 2009 |
A human–machine interface evaluation method: A difficulty evaluation method in information searching (DEMIS) | 5 | 0.49 | 2009 |
A method for identifying instrument faults in nuclear power plants possibly leading to wrong situation assessment | 2 | 0.49 | 2008 |
An analytical approach to quantitative effect estimation of operation advisory system based on human cognitive process using the Bayesian belief network | 2 | 0.37 | 2008 |
How to evaluate effectiveness in monitoring and detection tasks in nuclear power plants? | 0 | 0.34 | 2007 |
Experimental effect estimation of an integrated decision support system to aid operator's cognitive activities for nuclear power plants | 0 | 0.34 | 2007 |
The effect of information types on diagnostic strategies in the information aid | 2 | 0.49 | 2007 |
A probabilistic approach for determining the control mode in CREAM | 20 | 1.49 | 2006 |
Software design specification and analysis technique (SDSAT) for the development of safety-critical systems based on a programmable logic controller (PLC) | 0 | 0.34 | 2006 |
A method for evaluating fault coverage using simulated fault injection for digitalized systems in nuclear power plants | 0 | 0.34 | 2006 |
Reliability assessment of embedded digital system using multi-state function | 1 | 0.56 | 2006 |
Testing digital safety system software with a testability measure based on a software fault tree | 3 | 0.43 | 2006 |
A computational model for knowledge-driven monitoring of nuclear power plant operators based on information theory | 4 | 0.76 | 2006 |
An analytic model for situation assessment of nuclear power plant operators based on Bayesian inference | 12 | 1.31 | 2006 |
A computational method for probabilistic safety assessment of I&C systems and human operators in nuclear power plants | 6 | 0.63 | 2006 |
An effective technique for the software requirements analysis of NPP safety-critical systems, based on software inspection, requirements traceability, and formal specification | 0 | 0.34 | 2005 |
Development of a verification method for timed function blocks using ESDT and SMV | 1 | 0.37 | 2004 |
Reply to “Comment on: Development of a safety critical software requirements verification method with combined CPN and PVS: a nuclear power plant protection system application” | 0 | 0.34 | 2004 |
Software design specification and analysis technique for the safety critical software based on programmable logic controller (PLC) | 1 | 0.52 | 2004 |
A method for risk-informed safety significance categorization using the analytic hierarchy process and bayesian belief networks | 6 | 2.72 | 2004 |
A method of formal requirement analysis for NPP I&C systems based on UML modeling with software cost reduction | 2 | 0.40 | 2003 |
Systematic evaluation of fault trees using real-time model checker UPPAAL | 5 | 0.50 | 2003 |
A quantitative approach to modeling the information flow of diagnosis tasks in nuclear power plants | 0 | 0.34 | 2003 |
Hidden Markov Model-Based Real-Time Transient Identifications In Nuclear Power Plants | 0 | 0.34 | 2002 |
Experimental analysis of specification language diversity impact on NPP software diversity | 1 | 0.35 | 2002 |
Reliability graph with general gates: an intuitive and practical method for system reliability analysis | 8 | 1.31 | 2002 |
Information theoretic approach to man-machine interface complexity evaluation | 4 | 0.58 | 2001 |
Dependability estimation of a digital system with consideration of software masking effects on hardware faults | 0 | 0.34 | 2001 |
Automatic Fault Diagnosis Method For Resistive Network Using Multiple Excitations | 2 | 2.55 | 1996 |
Towards increasing the learning speed of gradient descent method in fuzzy system | 2 | 0.49 | 1996 |