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Passive system reliability analysis using Response Conditioning Method with an application to failure frequency estimation of Decay Heat Removal of PFBR

机译:响应条件法的被动系统可靠性分析及其在PFBR衰减热失效频率估计中的应用

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摘要

Innovative nuclear reactor designs include passive means to achieve high reliability in accomplishing safety functions. Functional reliability analyses of passive systems include Monte Carlo sampling of system uncertainties, followed by propagation through mechanistic system models. For complex passive safety systems of high reliability, Monte Carlo simulations using mechanistic codes are computationally expensive and often become prohibitive. Passive system reliability analysis using recently proposed Response Conditioning Method, which incorporates the insights obtained from approximate solutions like response surfaces in simulations to obtain computationally efficient and consistent probability estimates, is presented in this paper. The method is applied to evaluate the reliability of passive Decay Heat Removal (DHR) system of Indian Prototype Fast Breeder Reactor (PFBR). The accuracy as well as efficiency of the method is compared with direct Monte Carlo simulation. The variability of the reliability values is estimated using bootstrap technique. The system abilities, to prevent critical structural damage as well as to ensure operational safety, are quantitatively ascertained. The system functional failure probabilities are integrated with hardware failure probabilities and the inclusion of passive system unreliability in Probabilistic Safety Assessment is demonstrated.
机译:创新的核反应堆设计包括被动装置,以在实现安全功能方面实现高度可靠性。被动系统的功能可靠性分析包括系统不确定性的蒙特卡洛采样,然后通过机械系统模型进行传播。对于具有高可靠性的复杂被动安全系统,使用机械代码进行的蒙特卡洛模拟计算量大,并且经常变得令人望而却步。本文介绍了使用最近提出的响应条件方法进行无源系统可靠性分析的方法,该方法结合了从近似解决方案(如响应面)中获得的见解,从而获得了计算有效且一致的概率估计。该方法用于评估印度原型快中子增殖堆(PFBR)的被动衰变除热(DHR)系统的可靠性。该方法的准确性和效率与直接蒙特卡洛模拟进行了比较。可靠性值的可变性是使用自举技术估算的。定量确定了防止重大结构损坏以及确保操作安全的系统能力。系统功能故障概率与硬件故障概率集成在一起,并证明了在概率安全评估中包括被动系统不可靠性。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2011年第6期|p.2257-2270|共14页
  • 作者单位

    AERB-Safety Research Institute, Kalpakkam 603102, Tamilnadu, India;

    Indira Gandhi Centre [or Atomic Research, Kalpakkam 603102, Tamilnadu, India;

    Indira Gandhi Centre [or Atomic Research, Kalpakkam 603102, Tamilnadu, India;

    AERB-Safety Research Institute, Kalpakkam 603102, Tamilnadu, India;

    AERB-Safety Research Institute, Kalpakkam 603102, Tamilnadu, India;

    Indira Gandhi Centre [or Atomic Research, Kalpakkam 603102, Tamilnadu, India;

  • 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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