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Uncertainty and sensitivity analyses for age-dependent unavailability model integrating test and maintenance

机译:结合测试和维护的与年龄相关的不可用性模型的不确定性和敏感性分析

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摘要

The interest in operational lifetime extension of the existing nuclear power plants is growing. Consequently, plants life management programs, considering safety components ageing, are being developed and employed. Ageing represents a gradual degradation of the physical properties and functional performance of different components consequently implying their reduced availability. Analyses, which are being made in the direction of nuclear power plants lifetime extension are based upon components ageing management programs. On the other side, the large uncertainties of the ageing parameters as well as the uncertainties associated with most of the reliability data collections are widely acknowledged.This paper addresses the uncertainty and sensitivity analyses conducted utilizing a previously developed age-dependent unavailability model, integrating effects of test and maintenance activities, for a selected stand-by safety system in a nuclear power plant. The most important problem is the lack of data concerning the effects of ageing as well as the relatively high uncertainty associated to these data, which would correspond to more detailed modelling of ageing.A standard Monte Carlo simulation was coded for the purpose of this paper and utilized in the process of assessment of the component ageing parameters uncertainty propagation on system level. The obtained results from the uncertainty analysis indicate the extent to which the uncertainty of the selected component ageing data set influences the performed unavailability calculations on system level, as well as they present sensitivity insights on the equipment. Sensitivity analyses were additionally conducted. The obtained results indicate sensitivity insights associated to the coded Monte Carlo simulation itself as well as component ageing effects sensitivity judgements related to the selected system unavailability calculation.
机译:对延长现有核电厂使用寿命的兴趣正在增长。因此,考虑到安全组件的老化,正在开发和采用植物寿命管理程序。老化表示不同组件的物理性能和功能性能逐渐下降,因此暗示它们的可用性降低。朝核电厂寿命延长方向进行的分析是基于组件老化管理程序的。另一方面,人们广泛认可了老化参数的巨大不确定性以及与大多数可靠性数据收集相关的不确定性。本文探讨了利用先前开发的基于年龄的不可用性模型进行的不确定性和敏感性分析,综合了影响核电厂中选定的备用安全系统的测试和维护活动。最重要的问题是缺少有关老化影响的数据以及与这些数据相关的相对较高的不确定性,这将对应于更详细的老化建模。为此,对标准的蒙特卡洛模拟进行了编码在评估组件老化参数过程中的不确定性在系统级别的传播。从不确定性分析中获得的结果表明,所选组件老化数据集的不确定性在多大程度上影响了系统级执行的不可用性计算,以及它们在设备上的敏感性。另外进行了敏感性分析。获得的结果表明与编码的蒙特卡洛模拟本身相关的灵敏度洞察力,以及与所选系统不可用性计算相关的组件老化效应灵敏度判断。

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  • 来源
    《Nuclear Engineering and Design》 |2012年第5期|p.128-135|共8页
  • 作者

    Dusko Kancev; Marko Cepin;

  • 作者单位

    Reactor Engineering Division, JozefStefan Institute, Jamova 39, SI-1000 Ljubljana, Slovenia;

    Faculty of Electrical Engineering, University of Ljubljana, TriaSka 25, SI-1000 Ljubljana, Slovenia;

  • 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);
  • 原文格式 PDF
  • 正文语种 eng
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