首页> 外文会议>International Congress on Advances in Nuclear Power Plants >Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors (1) Project overviews
【24h】

Probabilistic Risk Assessment Method Development for High Temperature Gas-cooled Reactors (1) Project overviews

机译:高温气冷反应堆的概率风险评估方法(1)项目概述

获取原文
获取外文期刊封面目录资料

摘要

Japan Atomic Energy Agency, in conjunction with Tokyo City University, The University of Tokyo and JGC Corporation, have started development of a probabilistic risk assessment (PRA) method considering the safety and design features of High Temperature Gas-cooled Reactor (HTGR). The primary objective of the project is to develop a seismic PRA method which enables to provide a reasonably complete identification of accident scenario including a loss of safety function in passive system, structure and components. In addition, we aim to develop a basis for guidance to implement the PRA. This paper provides the overview of the activities including development of a system analysis method for multiple failures, a component failure data using the operation and maintenance experience in the High Temperature Engineering Test Reactor (HTTR), seismic fragility evaluation method, and mechanistic source term evaluation method considering failures in core graphite components and reactor building.
机译:日本原子能机构与东京市大学,东京大学和JGC公司一起开始开发概率风险评估(PRA)方法,考虑了高温气体冷却反应器(HTGR)的安全性和设计特征。该项目的主要目标是开发一种地震PRA方法,使能够合理地完全识别事故情景,包括无源系统,结构和组件中的安全功能损失。此外,我们的目标是为实施PRA的指导制定一个基础。本文提供了该活动的概述,包括开发系统分析方法,用于多次故障,使用高温工程测试反应堆(HTTR),地震脆性评估方法和机械源期限评估中的部件故障数据考虑核心石墨部件和反应堆建筑物失败的方法。

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