首页> 外文期刊>International Journal of Control, Automation, and Systems >A Safety Assessment Methodology for a Digital Reactor Protection System
【24h】

A Safety Assessment Methodology for a Digital Reactor Protection System

机译:数字反应堆保护系统的安全评估方法

获取原文
获取原文并翻译 | 示例
获取外文期刊封面目录资料

摘要

The main function of a reactor protection system is to maintain the reactor core integrity and the reactor coolant system pressure boundary. Generally, the reactor protection system adopts the 2-out-of-m redundant architecture to assure a reliable operation. This paper describes the safety assessment of a digital reactor protection system using the fault tree analysis technique. The fault tree technique can be expressed in terms of combinations of the basic event failures such as the random hardware failures, common cause failures, operator errors, and the fault tolerance mechanisms implemented in the reactor protection system. In this paper, a prediction method of the hardware failure rate is suggested for a digital reactor protection system, and applied to the reactor protection system being developed in Korea to identify design weak points from a safety point of view.
机译:反应堆保护系统的主要功能是维持反应堆堆芯完整性和反应堆冷却剂系统压力边界。通常,反应堆保护系统采用m的2-out冗余架构,以确保可靠的运行。本文介绍了使用故障树分析技术对数字反应堆保护系统进行安全评估的方法。故障树技术可以表示为基本事件故障的组合,例如随机硬件故障,共因故障,操作员错误以及在反应堆保护系统中实现的容错机制。本文提出了一种数字反应堆保护系统的硬件故障率预测方法,并将其应用于韩国正在开发的反应堆保护系统,以从安全角度识别设计薄弱点。

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