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Probabilistic risk assessment for a loss of coolant accident in McMaster Nuclear Reactor and application of reliability physics model for modeling human reliability.

机译:McMaster核反应堆中冷却剂损失事故的概率风险评估,以及用于建立人类可靠性模型的可靠性物理模型的应用。

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摘要

A probabilistic risk assessment (PRA) was conducted for a loss of coolant accident, (LOCA) in the McMaster Nuclear Reactor (MNR). A level 1 PRA was completed including event sequence modeling, system modeling, and quantification. To support the quantification of the accident sequence identified, data analysis using the Bayesian method and human reliability analysis (HRA) using the accident sequence evaluation procedure (ASEP) approach were performed.; Since human performance in research reactors is significantly different from that in power reactors, a time-oriented HRA model (reliability physics model) was applied for the human error probability (HEP) estimation of the core relocation. This model is based on two competing random variables: phenomenological time and performance time. The response surface and direct Monte Carlo simulation with Latin Hypercube sampling were applied for estimating the phenomenological time, whereas the performance time was obtained from interviews with operators. An appropriate probability distribution for the phenomenological time was assigned by statistical goodness-of-fit tests. The human error probability (HEP) for the core relocation was estimated from these two competing quantities: phenomenological time and operators' performance time. The sensitivity of each probability distribution in human reliability estimation was investigated. In order to quantify the uncertainty in the predicted HEPs, a Bayesian approach was selected due to its capability of incorporating uncertainties in model itself and the parameters in that model. The HEP from the current time-oriented model was compared with that from the ASEP approach. Both results were used to evaluate the sensitivity of alternative huinan reliability modeling for the manual core relocation in the LOCA risk model. This exercise demonstrated the applicability of a reliability physics model supplemented with a. Bayesian approach for modeling human reliability and its potential usefulness of quantifying model uncertainty as sensitivity analysis in the PRA model.
机译:对麦克马斯特核反应堆(MNR)中的冷却剂损失事故(LOCA)进行了概率风险评估(PRA)。完成了1级PRA,包括事件序列建模,系统建模和量化。为了支持对确定的事故序列进行量化,使用贝叶斯方法进行了数据分析,并使用事故序列评估程序(ASEP)方法进行了人员可靠性分析(HRA)。由于研究堆中的人员性能与动力堆中的人员性能显着不同,因此将时间导向的HRA模型(可靠性物理模型)应用于堆芯重定位的人为错误概率(HEP)估计。该模型基于两个相互竞争的随机变量:现象学时间和表演时间。响应面和采用拉丁超立方体采样的直接蒙特卡罗模拟被用于估计现象学时间,而表演时间则是从与操作员的访谈中获得的。通过统计拟合优度检验,为现象学时间分配了适当的概率分布。核心重新定位的人为错误概率(HEP)是从以下两个竞争量估算出来的:现象学时间和操作员的执行时间。研究了人类可靠性估计中每种概率分布的敏感性。为了量化预测的HEP中的不确定性,选择了一种贝叶斯方法,因为它具有将不确定性纳入模型本身和该模型中参数的能力。将当前面向时间的模型中的HEP与ASEP方法中的HEP进行了比较。这两个结果均用于评估LOCA风险模型中替代的huinan可靠性模型对人工核心重新布置的敏感性。本练习演示了以a为补充的可靠性物理模型的适用性。贝叶斯方法对人类可靠性进行建模,以及量化模型不确定性作为PRA模型中的敏感性分析的潜在用处。

著录项

  • 作者

    Ha, Taesung.;

  • 作者单位

    McMaster University (Canada).;

  • 授予单位 McMaster University (Canada).;
  • 学科 Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2007
  • 页码 170 p.
  • 总页数 170
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

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