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Evaluation of operators' mental workload of human-system interface automation in the advanced nuclear power plants

机译：评估先进核电厂中人机界面自动化操作员的心理工作量

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摘要

It has been expected that the automation of certain tasks in a control room would help decrease operators' mental workload, enhance situation awareness, and improve the whole system performance. However, there have been too many automation-induced system failures that would warrant a fresh look on the influences of automation. Automation problems include the reduction in the operator's system awareness, an increase in monitoring workload, and the degradation in manual skills. This study evaluates operators' mental workload and system performance during a human-system interface (HSI) automation in an advanced nuclear power plant (NPP). The reactor shutdown task and alarm reset task simulations were conducted in this study to evaluate operators' mental workload and performance. The results of this study indicated that for ensuring safe operating in NPPs, the design of automation needs to be carefully implemented. Task characteristics and degrees of automation should be carefully evaluated while designing HSIs. The reactor shutdown tasks studied in this paper suggest that a high level of automation design for the long period and low workload would be sufficient. On the other hand, the degree of automation of alarm reset task does not show a significant difference to the operator's mental workload. In conclusion, the human-system interface automation in advanced NPPs is suggested to be more flexible and needs to be continually improved.
机译：可以预期，控制室中某些任务的自动化将有助于减少操作员的心理工作量，增强态势感知并改善整个系统性能。但是，由自动化引起的系统故障太多，需要重新审视自动化的影响。自动化问题包括降低操作员的系统意识，增加监视工作量以及降低手动技能。这项研究评估了高级核电厂（NPP）中人机界面（HSI）自动化过程中操作员的心理工作量和系统性能。在这项研究中进行了反应堆关闭任务和警报重置任务模拟，以评估操作员的心理工作量和性能。这项研究的结果表明，为了确保在核电厂中安全运行，需要认真执行自动化设计。在设计HSI时，应仔细评估任务特征和自动化程度。本文研究的反应堆关闭任务表明，长期的高水平自动化设计和低工作量就足够了。另一方面，警报重置任务的自动化程度与操作员的精神工作量没有显着差异。总之，建议先进NPP中的人机界面自动化更加灵活，并且需要不断改进。

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  • 来源
    《Nuclear Engineering and Design》 |2009年第11期|2537-2542|共6页
  • 作者

    Yung-Tsan Jou; Tzu-Chung Yenn; Chiuhsiang Joe Lin; Chih-Wei Yang; Chih-Cheng Chiang;

  • 作者单位

    Department of Industrial and Systems Engineering, Chung-Yuan Christian University 200, Chung Pei Rd., Chung-Li 32023, Taiwan, ROC;

    Institute of Nuclear Energy Research, 1000, Wunhua Rd., Jiaan Village, Longtan Township, Taoyuan 32546, Taiwan, ROC;

    Department of Industrial and Systems Engineering, Chung-Yuan Christian University 200, Chung Pei Rd., Chung-Li 32023, Taiwan, ROC;

    Institute of Nuclear Energy Research, 1000, Wunhua Rd., Jiaan Village, Longtan Township, Taoyuan 32546, Taiwan, ROC;

    Department of Industrial and Systems Engineering, Chung-Yuan Christian University 200, Chung Pei Rd., Chung-Li 32023, Taiwan, ROC;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
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  • 正文语种 eng
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