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Hyun Gook Kang · Study

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Hyun Gook Kang

19 works· latest 2021· 3 institutionscluster: provisionalORCID 0000-0002-8216-218X

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i1019

Citations461

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Most cited in this library

An analysis of safety-critical digital systems for risk-informed design2002 · 55 citations
Dynamic risk assessment with bayesian network and clustering analysis2020 · 51 citations
Probabilistic risk assessment on maritime spent nuclear fuel transportation (Part II: Ship collision probability)2017 · 45 citations
System risk quantification and decision making support using functional modeling and dynamic Bayesian network2021 · 39 citations
AN OVERVIEW OF RISK QUANTIFICATION ISSUES FOR DIGITALIZED NUCLEAR POWER PLANTS USING A STATIC FAULT TREE2009 · 25 citations

Works

19 shown

System risk quantification and decision making support using functional modeling and dynamic Bayesian network

Reliability Engineering & System Safety·2021·4 authors·Open access

39citations

Dynamic risk assessment with bayesian network and clustering analysis

Reliability Engineering & System Safety·2020·3 authors·Open access

51citations

Systematic development of scenarios caused by cyber-attack-induced human errors in nuclear power plants

Reliability Engineering & System Safety·2017·4 authors

24citations

Risk assessment of safety data link and network communication in digital safety feature control system of nuclear power plant

Annals of Nuclear Energy·2017·4 authors

15citations

Probabilistic risk assessment on maritime spent nuclear fuel transportation (Part II: Ship collision probability)

Reliability Engineering & System Safety·2017·2 authors

45citations

Reliability modeling of safety-critical network communication in a digitalized nuclear power plant

Reliability Engineering & System Safety

·2015

·6 authors

20citations

Integrated societal risk assessment framework for nuclear power and renewable energy sources

Nuclear Engineering and Technology·2015·2 authors·Open access

18citations

ADVANCED MMIS TOWARD SUBSTANTIAL REDUCTION IN HUMAN ERRORS IN NPPS

Nuclear Engineering and Technology·2013·6 authors·Open access

23citations

An empirical study on the basic human error probabilities for NPP advanced main control room operation using soft control

Nuclear Engineering and Design·2013·6 authors

21citations

Unavailability and spurious operation probability of k-out-of-n reactor protection systems in consideration of CCF

Annals of Nuclear Energy·2012·2 authors

13citations

FAULT DETECTION COVERAGE QUANTIFICATION OF AUTOMATIC TEST FUNCTIONS OF DIGITAL I＆C SYSTEM IN NPPS

Nuclear Engineering and Technology·2012·5 authors·Open access

21citations

Reliability assessment method for NPP digital I&C systems considering the effect of automatic periodic tests

Annals of Nuclear Energy·2010·4 authors·Open access

12citations

A model for estimation of reactor spurious shutdown rate considering maintenance human errors in reactor protection system of nuclear power plants

Nuclear Engineering and Design·2010·4 authors

16citations

AN OVERVIEW OF RISK QUANTIFICATION ISSUES FOR DIGITALIZED NUCLEAR POWER PLANTS USING A STATIC FAULT TREE

Nuclear Engineering and Technology·2009·6 authors·Open access

25citations

A Quantitative Study on Risk Issues in Safety Feature Control System Design in Digitalized Nuclear Power Plant

Journal of Nuclear Science and Technology·2008·2 authors·Open access

12citations

Application of condition-based HRA method for a manual actuation of the safety features in a nuclear power Plant

Reliability Engineering & System Safety·2005·2 authors

19citations

A PSA-based vital area identification methodology development

Reliability Engineering & System Safety·2003·6 authors

18citations

An analysis of safety-critical digital systems for risk-informed design

Reliability Engineering & System Safety·2002·2 authors

55citations

A Quantitative Study on Important Factors of the PSA of Safety-Critical Digital Systems

Nuclear Engineering and Technology·2001·2 authors

14citations