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Seung-Cheol Jang · Study

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Seung-Cheol Jang

10 works· latest 2015· 1 institutionscluster: provisional

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Citations195

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Most cited in this library

Human Error Mode Identification for NPP Main Control Room Operations Using Soft Controls2011 · 42 citations
AN OVERVIEW OF RISK QUANTIFICATION ISSUES FOR DIGITALIZED NUCLEAR POWER PLANTS USING A STATIC FAULT TREE2009 · 25 citations
FAULT DETECTION COVERAGE QUANTIFICATION OF AUTOMATIC TEST FUNCTIONS OF DIGITAL I＆C SYSTEM IN NPPS2012 · 21 citations
Estimating the response times of human operators working in the main control room of nuclear power plants based on the context of a seismic event – A case study2015 · 21 citations
Application of condition-based HRA method for a manual actuation of the safety features in a nuclear power Plant2005 · 19 citations

Works

10 shown

Estimating the response times of human operators working in the main control room of nuclear power plants based on the context of a seismic event – A case study

Annals of Nuclear Energy·2015·5 authors

21citations

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

Human Error Mode Identification for NPP Main Control Room Operations Using Soft Controls

Journal of Nuclear Science and Technology·2011·3 authors·Open access

42citations

Some empirical insights on diagnostic performance of the operating crew in a computer‐based advanced control room

Human Factors and Ergonomics in Manufacturing & Service Industries·2010·5 authors

14citations

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

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

An analytic solution for a fault tree with circular logics in which the systems are linearly interrelated

Reliability Engineering & System Safety·2006·2 authors

17citations

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

ATWS Frequency Quantification Focusing on Digital I&C Failures

Nuclear Engineering and Technology·2004·3 authors

12citations