首页 | 官方网站   微博 | 高级检索  
     

核电厂堆腔冷却状态监测研究
引用本文:何鹏,陈静,李小芬,何正熙,朱加良,徐涛,李红霞.核电厂堆腔冷却状态监测研究[J].核动力工程,2020,41(5):94-98.
作者姓名:何鹏  陈静  李小芬  何正熙  朱加良  徐涛  李红霞
作者单位:中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213,中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213,中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213,中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213,中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213,中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213,中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213
摘    要:为判断严重事故下堆腔的事故进程和堆腔注水策略启动后的执行效果,分析了严重事故条件下不同注水速度下堆腔多项物性参数状态的发展序列,对比研究了传统二代加核电厂、改进型二代加核电厂、华龙一号核电厂的监测手段;通过优化温度测量仪表、液位测量仪表、监测系统的功能设计和计算方法,最终在华龙一号核电厂中设计了完善的监测系统。此监测系统实现了严重事故下反应堆压力容器(RPV)失效前的事故状态监测、堆腔注水策略启动后缓解措施投运情况监测以及RPV破损后熔融物状态监测,有效完成了严重事故条件下堆腔状态监测需求。 

关 键 词:堆腔冷却    严重事故监测    堆腔注水    严重事故缓解    熔融物滞留    熔融物探测    堆芯熔化

Research on Monitoring of Reactor Cavity Cooling Status for NPPs
He Peng,Chen Jing,Li Xiaofen,He Zhengxi,Zhu Jialiang,Xu Tao,Li Hongxia.Research on Monitoring of Reactor Cavity Cooling Status for NPPs[J].Nuclear Power Engineering,2020,41(5):94-98.
Authors:He Peng  Chen Jing  Li Xiaofen  He Zhengxi  Zhu Jialiang  Xu Tao  Li Hongxia
Abstract:In order to justify the accident progresses of the cavity and the implementation effect of the cavity injection strategy that is activated under the severe accident condition, the evolution sequence of several cavity physical property parameters of different injection water velocity under severe accident condition is analyzed, and the monitoring measures in the conventional generation 2nd NPP, the improved generation 2nd plus NPP and the HPR1000 NPP are comparatively studied; Based on the optimization of the functional design and algorithm of the temperature measurement instrumentation, water level measurement instrumentation and monitoring system, the monitoring system of the HPR1000 NPP is finally designed. The monitoring system can conduct the accident status monitoring before the failure of the pressure vessel under the severe accident condition, the operation condition monitoring after the activation of the cavity injection strategy, and the molten debris status monitoring after the failure of the pressure vessel, and can satisfy the demand on the cavity status monitoring requirement under the severe accident condition. 
Keywords:
本文献已被 万方数据 等数据库收录!
点击此处可从《核动力工程》浏览原始摘要信息
点击此处可从《核动力工程》下载全文
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司    京ICP备09084417号-23

京公网安备 11010802026262号