首页> 外文会议>International congress on advances in nuclear power plants >Investigations on Optimization of Accident Management Measures following a Station Blackout Accident in a WER-1000 Pressurized Water Reactor
【24h】

Investigations on Optimization of Accident Management Measures following a Station Blackout Accident in a WER-1000 Pressurized Water Reactor

机译:WER-1000压水堆站停电事故后事故管理措施的优化研究

获取原文

摘要

The reactor safety issues are of primary importance for preserving the health of the population and ensuring no release of radioactivity and fission products into the environment. A part of the nuclear research focuses on improvement of the safety of existing nuclear power plants. Studies, research and efforts are a continuing process at improving the safety and reliability of existing and newly developed nuclear power plants at prevention of a core melt accident. Station blackout (loss of AC power supply) is one of the dominant accidents taken into consideration at performing accident analysis. In case of multiple failures of safety systems it leads to a severe accident. To prevent an accident to turn into a severe one or to mitigate the consequences, accident management measures must be performed. The present paper outlines possibilities for application and optimization of accident management measures following a station blackout accident. Assessed is the behaviour of the nuclear power plant during a station blackout accident without accident management measures and with application of primary/secondary side oriented accident management measures. Discussed are the possibilities for operators' intervention and the influence of the performed accident management measures on the course of the accident. Special attention has been paid to the effectiveness of the passive feeding and physical phenomena having an influence on the system behaviour. The performed simulations show that the effectiveness of the secondary side feeding procedure can be limited due to an early evaporation or flashing effects in the feed water system. The analyzed cases show that the effectiveness of the accident management measures strongly depends on the initiation criteria applied for depressurization of the reactor coolant system.
机译:反应堆安全问题对于维护人民的健康并确保放射性和裂变产物不会释放到环境中至关重要。核研究的一部分集中于改善现有核电厂的安全性。研究,研究和努力是提高现有和新建核电厂安全性和可靠性的持续过程,可预防堆芯熔化事故。车站停电(交流电源丢失)是进行事故分析时要考虑的主要事故之一。如果安全系统发生多次故障,则会导致严重事故。为了防止事故演变为严重事故或减轻后果,必须执行事故管理措施。本文概述了车站停电事故后应用和优化事故管理措施的可能性。在没有事故管理措施的情况下,采用面向主/次方的事故管理措施,评估了核电站在停电事故中的行为。讨论了操作员干预的可能性以及所采取的事故管理措施对事故过程的影响。已经特别注意了被动馈电的有效性和对系统行为有影响的物理现象。进行的模拟表明,由于给水系统中的早期蒸发或闪蒸效应,次级侧给水程序的有效性可能受到限制。分析的案例表明,事故管理措施的有效性在很大程度上取决于应用于反应堆冷却剂系统降压的初始标准。

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