首页> 外文会议>International conference on nuclear engineering >RELIABILITY ASSESSMENT OF REACTOR AP1000 PASSIVE ERVC SYSTEM
【24h】

RELIABILITY ASSESSMENT OF REACTOR AP1000 PASSIVE ERVC SYSTEM

机译:反应堆AP1000被动ERVC系统的可靠性评估

获取原文

摘要

As the safety requirements level of nuclear power plant is gradually improving, more and more passive systems are used in the advanced type reactors. However, the reliability evaluation work for these passive systems is still in the primary stage. Therefore, in this paper the work is started based on the reliability evaluation process of passive system, simulates the physical process of passive systems by RELAP thermal hydraulics program, and evaluates the reliability of AP1000 External Reactor Vessel Cooling (ERVC) system. After the large number of calculations the cumulative density distribution curve of the temperature in lower head of the reactor pressure vessel is obtained, so by combining with specific success criteria the reliability of AP1000 ERVC system can be obtained, and this reliability evaluation result of ERVC system can be used in the PSA model to better guide the design of nuclear power plants and improve the safety of nuclear power plants.
机译:随着核电厂安全要求水平的逐步提高,先进反应堆中越来越多地采用无源系统。但是,这些无源系统的可靠性评估工作仍处于初级阶段。因此,本文基于被动系统的可靠性评估过程开始工作,通过RELAP热工程序模拟被动系统的物理过程,并评估AP1000外部反应堆容器冷却(ERVC)系统的可靠性。经过大量的计算,得到了反应堆压力容器下扬程温度的累积密度分布曲线,因此,结合具体的成功标准,可以得出AP1000 ERVC系统的可靠性,并得到该ERVC系统的可靠性评估结果。 PSA模型可用于更好地指导核电厂的设计并提高核电厂的安全性。

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