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Human error and the associated recovery probabilities for soft control being used in the advanced MCRs of NPPs

机译:NPP的高级MCR中使用了人为错误和相关的软控制恢复概率

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Since the Three Mile Island (TMI)-2 accident, human error has been recognized as one of the main causes of Nuclear Power Plant (NPP) accidents, and numerous studies related to Human Reliability Analysis (HRA) have been carried out. Most of these studies were focused on considering the conventional Main Control Room (MCR) environment. However, the operating environment of MCRs in NPPs has changed with the adoption of new human-system interfaces (HSI) largely based on up-to-date digital technologies. The MCRs that include these digital and computer technologies, such as large display panels, computerized procedures, and soft controls, are called advanced MCRs. Among the many features of advanced MCRs, soft controls are a particularly important because operating actions in advanced MCRs are performed by soft control. Due to the difference in interfaces between soft control and hardwired conventional controls, different HEP should be used in the HRA for advanced MCRs. Unfortunately, most current HRA databases deal with operations in conventional MCRs and are not explicitly designed to deal with digital Human System Interface (HSI). For this reason, empirical human error and the associated error recovery probabilities were collected from the mockup of an advanced MCR equipped with soft controls. To this end, small-scaled experiments are conducted with 48 graduated students in the department of nuclear engineering in Korea Advanced Institute of Science and Technology (KAIST) are participated, and accident scenarios are designed with respect to the typical Design Basis Accidents (DBAs) in NPPs, such as Steam Generator Tube Rupture (SGTR), Loss of Coolant Accident (LOCA) and Excess Steam Demand Event (ESDE). After that, the Bayesian update is conducted in order to extract the 5% and 95% quantiles of empirical human error and the associated recovery failure probabilities. (C) 2015 Elsevier Ltd. All rights reserved.
机译:自三英里岛(TMI)-2事故以来,人为错误已被认为是核电厂(NPP)事故的主要原因之一,并且已经进行了许多与人的可靠性分析(HRA)相关的研究。这些研究大多数集中在考虑常规的主控制室(MCR)环境。但是,随着主要基于最新数字技术的新人机界面(HSI)的采用,核电厂中MCR的操作环境发生了变化。包括这些数字和计算机技术的MCR(例如大型显示面板,计算机化程序和软控制)被称为高级MCR。在高级MCR的许多功能中,软控制特别重要,因为高级MCR中的操作是通过软控制执行的。由于软控制和硬连线常规控制之间的接口不同,HRA中应将不同的HEP用于高级MCR。不幸的是,当前的大多数HRA数据库都处理常规MCR中的操作,并且没有明确设计为处理数字人机界面(HSI)。因此,从配备了软控件的高级MCR的模型中收集了经验性人为错误和相关的错误恢复概率。为此,参加了韩国高级科学技术学院(KAIST)核工程系的48名研究生的小规模实验,并针对典型的设计基准事故(DBA)设计了事故场景。在NPP中,例如蒸汽发生器管破裂(SGTR),冷却液损失事故(LOCA)和过量蒸汽需求事件(ESDE)。之后,进行贝叶斯更新,以提取经验性人为错误和相关的恢复失败概率的5%和95%的分位数。 (C)2015 Elsevier Ltd.保留所有权利。

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