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Investigating the effect of communication characteristics on crew performance under the simulated emergency condition of nuclear power plants

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  • Park, Jinkyun
  • Jung, Wondea
  • Yang, Joon-Eon

Abstract

It is well known that the safety of large process control systems could be significantly affected by the communication characteristics of crews that have a responsibility for their operations. Accordingly, many researchers have spent huge amount of effort to grasp the relationship between the characteristics of crew communications and the associated crew performance. Unfortunately, in the case of nuclear power plants (NPPs), it seems that most of existing studies have tried to identify the relationship between the characteristics of crew communications and the associated crew performance using empirical observations without a firm technical underpinning. For these reasons, Park suggested a novel framework that is able to represent the characteristics of crew communications based on social network analysis (SNA) metrics. In order to confirm the appropriateness of the suggested framework, in this study, the characteristics of crew communications that are gathered from the simulated emergency condition of NPPs are additionally compared with the associated crew performance data. As a consequence, it is observed that there are significant relationships between communication characteristics and the associated crew performance. Therefore, it is reasonable to expect that the characteristics of crew communications can be properly grasped using the suggested framework.

Suggested Citation

  • Park, Jinkyun & Jung, Wondea & Yang, Joon-Eon, 2012. "Investigating the effect of communication characteristics on crew performance under the simulated emergency condition of nuclear power plants," Reliability Engineering and System Safety, Elsevier, vol. 101(C), pages 1-13.
  • Handle: RePEc:eee:reensy:v:101:y:2012:i:c:p:1-13
    DOI: 10.1016/j.ress.2012.01.003
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    References listed on IDEAS

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    1. Park, Jinkyun, 2011. "The use of a social network analysis technique to investigate the characteristics of crew communications in nuclear power plants—A feasibility study," Reliability Engineering and System Safety, Elsevier, vol. 96(10), pages 1275-1291.
    2. Kim, Man Cheol & Seong, Poong Hyun, 2006. "A computational method for probabilistic safety assessment of I&C systems and human operators in nuclear power plants," Reliability Engineering and System Safety, Elsevier, vol. 91(5), pages 580-593.
    3. Xiang, Fang & Xuhong, He & Bingquan, Zhao, 2008. "Research of psychological characteristics and performance relativity of operators," Reliability Engineering and System Safety, Elsevier, vol. 93(8), pages 1244-1249.
    4. Chung, Yun Hyung & Yoon, Wan Chul & Min, Daihwan, 2009. "A model-based framework for the analysis of team communication in nuclear power plants," Reliability Engineering and System Safety, Elsevier, vol. 94(6), pages 1030-1040.
    5. Jinkyun Park, 2009. "The Complexity of Proceduralized Tasks," Springer Series in Reliability Engineering, Springer, number 978-1-84882-791-2, January.
    6. Kirwan, Barry & Gibson, W. Huw & Hickling, Brian, 2008. "Human error data collection as a precursor to the development of a human reliability assessment capability in air traffic management," Reliability Engineering and System Safety, Elsevier, vol. 93(2), pages 217-233.
    7. Kim, Man Cheol & Seong, Poong Hyun, 2008. "A method for identifying instrument faults in nuclear power plants possibly leading to wrong situation assessment," Reliability Engineering and System Safety, Elsevier, vol. 93(2), pages 316-324.
    8. Zhang, Li & He, Xuhong & Dai, Li-Cao & Huang, Xiang-Rui, 2007. "The simulator experimental study on the operator reliability of Qinshan nuclear power plant," Reliability Engineering and System Safety, Elsevier, vol. 92(2), pages 252-259.
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    Cited by:

    1. Park, Jinkyun & Kim, Yochan, 2018. "A novel speech-act coding scheme to visualize the intention of crew communications to cope with simulated off-normal conditions of nuclear power plants," Reliability Engineering and System Safety, Elsevier, vol. 178(C), pages 236-246.

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