2009
DOI: 10.3327/jnst.46.424
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Modeling of a Dependence between Human Operators in Advanced Main Control Rooms

Abstract: For the human reliability analysis of main control room (MCR) operations, not only parameters such as the given situation and capability of the operators but also the dependence between the actions of the operators should be considered because MCR operations are team operations. The dependence between operators might be more prevalent in an advanced MCR in which operators share the same information using a computerized monitoring system or a computerized procedure system. Therefore, this work focused on the co… Show more

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Cited by 2 publications
(2 citation statements)
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“…Human reliability analysis must conclude an assessment of dependence between human errors, as probability of operators' failure is higher if he failed during the previous task than if he succeeded (Zio, 2009). It's important to consider the dependence between operators' actions when performing a human reliability analysis of control room operations, as they are team operations (Lee, 2009). C epin (2008) used the method of DEPEND-HRA, which distinguishes dependency for pre-initiator events from dependency for initiator and post-initiator events, on real plantspecific human reliability analysis as a part of the probabilistic safety assessment of a nuclear power plant.…”
Section: Introductionmentioning
confidence: 99%
“…Human reliability analysis must conclude an assessment of dependence between human errors, as probability of operators' failure is higher if he failed during the previous task than if he succeeded (Zio, 2009). It's important to consider the dependence between operators' actions when performing a human reliability analysis of control room operations, as they are team operations (Lee, 2009). C epin (2008) used the method of DEPEND-HRA, which distinguishes dependency for pre-initiator events from dependency for initiator and post-initiator events, on real plantspecific human reliability analysis as a part of the probabilistic safety assessment of a nuclear power plant.…”
Section: Introductionmentioning
confidence: 99%
“…An operation failure could be caused by a mistake of an operator, hardware failures, or other reasons. [3][4][5][6][7][8] As digital and computer technologies have been adapted in NPPs, there have been many changes in the design of MCRs.…”
Section: Introductionmentioning
confidence: 99%