首页> 外文会议>International topical meeting on probabilistic safety assessment and analysis;PSA 2011 >RELIABILITY OF THE EPR FUEL POOL COOLING SYSTEM USING A DYNAMIC APPROACH
【24h】

RELIABILITY OF THE EPR FUEL POOL COOLING SYSTEM USING A DYNAMIC APPROACH

机译:动态方法在EPR燃油池冷却系统中的可靠性

获取原文

摘要

One of the important issues for PSA analysis is to fully consider safety systems with their dynamic behaviour and the possibility to include operational properties and procedures. In the static traditional approach, it is not easy to introduce such dynamic phenomena in a the event tree model and one may need to use some dynamic framework to solve such problems. In this paper, we consider the Boolean Markov Driven Processes (BDMP) to model a safety system of a nuclear power plant. The main objective is to model functional dependencies, component recoveries, time dependant or conditional failures/recoveries and the possibility to use special configurations with "extra"-alignments. Thanks to a declarative knowledge based tool, these features can be embedded in such models in a compact form that may be instantiated in different ways with respect to the configuration or state of the system. Indeed, the BDMP framework allows to define such dynamic models using a fault-tree like construction with interesting mathematical properties. In particular, the possibility to reduce the combinatorial explosion problems inherent to Markov models. This allows to quantify the models and get the different reliability measures in reasonable times. The dynamic approach offered by the BDMP is particularly useful to model very redundant systems such as FA3 EPR FCPS (Fuel Pool Cooling System). The FCPS consists in three trains: two identical main trains, each equipped with two pumps in parallel, and a third train, fully independent. The complexity of the dependencies between each line can only be apprehended by a dynamic model and the BDMP allows a more realistic approach to model accident scenarios. The BDMP model of the FCPS as well as the reliability results obtained are presented in this article.
机译:PSA分析的重要问题之一是充分考虑安全系统的动态行为,并考虑其运行特性和程序的可能性。在静态传统方法中,在事件树模型中引入这种动态现象并不容易,并且可能需要使用某种动态框架来解决此类问题。在本文中,我们考虑使用布尔马尔可夫驱动过程(BDMP)对核电厂的安全系统进行建模。主要目标是对功能依赖性,组件恢复,时间相关或有条件的故障/恢复进行建模,以及使用带有“额外”对齐的特殊配置的可能性。由于使用了基于声明性知识的工具,这些功能可以以紧凑的形式嵌入到此类模型中,可以相对于系统的配置或状态以不同的方式实例化这些特征。实际上,BDMP框架允许使用类似故障树的构造来定义此类动态模型,并具有有趣的数学特性。尤其是可以减少马尔可夫模型固有的组合爆炸问题。这样可以量化模型并在合理的时间内获得不同的可靠性指标。 BDMP提供的动态方法对于建模非常冗余的系统(例如FA3 EPR FCPS(燃料池冷却系统))特别有用。 FCPS由三列火车组成:两列完全相同的主列火车,每列均并联装有两个泵,第三列火车完全独立。每条线之间的依赖关系的复杂性只能通过动态模型来理解,而BDMP允许使用更为现实的方法来对事故场景进行建模。本文介绍了FCPS的BDMP模型以及获得的可靠性结果。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号