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Determination of Operator Action Times During a Loss-of-Feedwater Event Using Extreme Value Statistics

机译:使用极值统计确定缺水事件中操作员的动作时间

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摘要

The pursuit of more realistic models for nuclear power plant systems is becoming increasingly important and has led to an expansion in statistical uncertainty analysis coupled with the use of best-estimate predictions. Within these methodologies, derived acceptance criteria have been developed to ensure that the ultimate safety criteria are met with acceptably high levels of probability and confidence. The meeting of these derived criteria with a probability of 95% for a confidence interval of 95%, the 95/95 criteria, ensures consistency between analysis and instrumentation accuracy requirements set forth in ISA 67.04 standards. However, the application of these statistical methods to accidents requiring operator intervention, such as complete loss-of-feedwater events, has not previously been the topic of investigation. This paper applies the extreme value statistics (EVS) methodology to the steam generator-level transients predicted to result from a total loss-of-feedwater accident and compares the result to other uncertainty propagation methods and deterministic calculations. The transient was modeled using a full-circuit one-dimensional thermal-hydraulic code, and the epistemic and aleatory uncertainties inherent in the reactor are assessed. Based upon these results the available steam generator inventories at the time of trip were statistically determined, and subsequently, the available times for operator action were determined. Comparisons were made between the EVS methods and limiting deterministic analysis results for a standard CANDU 9 design as well as to other best-estimate and uncertainty-analysis techniques. Key uncertainties were identified based on phenomena identification and ranking tables and were confirmed through sensitivity studies. The requirement for operator-initiated actions for the EVS case was ~46 min with 95% probability and 95% confidence from the time of annunciation, and this was 30 min longer than the limiting deterministic case.
机译:追求更现实的核电厂系统模型变得越来越重要,并导致统计不确定性分析的扩展以及最佳估计的使用。在这些方法中,已经制定了派生的接受标准,以确保以可接受的高水平的概率和置信度满足最终的安全标准。以95%的置信区间95/95标准满足这些衍生标准的可能性为95%,从而确保了ISA 67.04标准中规定的分析和仪器精度要求之间的一致性。但是,将这些统计方法应用于需要操作员干预的事故,例如完全的给水损失事件,以前并不是研究的主题。本文将极值统计(EVS)方法应用于预计因总给水损失事故而导致的蒸汽发生器级瞬变,并将该结果与其他不确定性传播方法和确定性计算进行比较。使用全电路一维热工代码对瞬态进行建模,并对反应堆固有的认知和不确定性进行评估。根据这些结果,统计确定出行时的可用蒸汽发生器清单,然后确定操作员可用的时间。在标准的CANDU 9设计以及其他最佳估计和不确定性分析技术的EVS方法与确定性分析结果之间进行了比较。根据现象识别和排名表确定了关键的不确定性,并通过敏感性研究得到了确认。从通告之时起,EVS案例要求操作员启动操作的时间约为46分钟,概率为95%,置信度为95%,这比确定性限制案例要长30分钟。

著录项

  • 来源
    《Nuclear science and engineering》 |2010年第2期|151-161|共11页
  • 作者

    A. C. Morreale; D. R. Novog;

  • 作者单位

    McMaster University, Department of Engineering Physics 1280 Main Street West, Hamilton L8S 4L7, Ontario, Canada;

    McMaster University, Department of Engineering Physics 1280 Main Street West, Hamilton L8S 4L7, Ontario, Canada;

  • 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
  • 中图分类
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