首页 | 官方网站   微博 | 高级检索  
     

中国先进研究堆一次冷却剂回路密封垫破损事件分析与处理
引用本文:焦迪楠,甄建霄,朱吉印,丁丽,宁波.中国先进研究堆一次冷却剂回路密封垫破损事件分析与处理[J].原子能科学技术,2017,51(12):2357-2362.
作者姓名:焦迪楠  甄建霄  朱吉印  丁丽  宁波
作者单位:中国原子能科学研究院 反应堆工程技术研究部,北京102413
摘    要:本文介绍了中国先进研究堆(CARR)一次冷却剂回路密封垫破损事件以及运行人员对事件的处理过程,剖析了事件发生的根本原因即管路法兰原安装的缺陷,分析了事件后果影响,即造成冷却剂泄漏,指出该事件未对工作人员辐射安全造成影响,未对反应堆及关键系统设备造成影响,泄漏水均在厂房内,对环境无影响,反应堆各项参数均未超出技术规格书中规定的运行限值与条件。本文对事件的过程数据与安全分析报告的内容进行了分析比较,针对事件发生的原因以及处理过程中遇到的一些问题,按照纵深防御的原则,分别从密封垫选型更换、增设法兰防护套、增设渗漏信号以及加强控制技术等方面阐述了系统的改进及优化。

关 键 词:中国先进研究堆    密封垫破损    冷却剂泄漏    纵深防御

Analysis and Disposal for Sealing Gasket Breakage Event of Primary Coolant Loop in China Advanced Research Reactor
JIAO Di-nan,ZHEN Jian-xiao,ZHU Ji-yin,DING Li,NING Bo.Analysis and Disposal for Sealing Gasket Breakage Event of Primary Coolant Loop in China Advanced Research Reactor[J].Atomic Energy Science and Technology,2017,51(12):2357-2362.
Authors:JIAO Di-nan  ZHEN Jian-xiao  ZHU Ji-yin  DING Li  NING Bo
Affiliation:China Institute of Atomic Energy, P. O. Box 275-43, Beijing 102413, China
Abstract:The sealing gasket breakage event of primary coolant loop in China Advanced Research Reactor (CARR) and the event processing by operators of CARR were introduced in this paper. The reason of the event was original installation defects of pipeline flange, and consequences of this event causing loss of coolant were analyzed. It is shown that this event does not affect the radiation safety of workers and cause any impact on reactor and critical system and equipment. All of leakage water is collected in the plant of reactor, and it does not impact on environment. All parameters do not exceed the limits and conditions specified by safety technical specification. The event process data were analyzed and compared with the content of safety analysis report. For the cause of the event and some problems encountered in the process, according to the defense in depth policy, several system improvements and optimizations were elaborated, including gasket replacement, adding flange protective kit, adding leakage signal and strengthening control techniques etc.
Keywords:China Advanced Research Reactor  sealing gasket breakage  loss of coolant  defense-in-depth policy
本文献已被 CNKI 等数据库收录!
点击此处可从《原子能科学技术》浏览原始摘要信息
点击此处可从《原子能科学技术》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