具备三代核电安全功能特征的RCI系统冷却剂流道设计  

作　　者：邱阳[1] 杨敏[1] 谢国福[1] 陈海波[1] 杨立才[1] 

机构地区：[1]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,四川成都610041

出　　处：《科技视界》2021年第12期103-106,共4页Science & Technology Vision

摘　　要：田湾5、6号机组核岛设计在充分吸收福岛核事故经验反馈的基础上,采纳先进三代核电的熔融物堆内滞留(IVR)安全设计理念,设置了堆腔冷却剂注入(RCI)系统。为实现RCI功能,反应堆压力容器(RPV)保温层需与RPV以及堆坑壁之间形成具有一定间隙的稳定可靠的冷却剂流道,而该流道的设置给RPV保温层带来了支承热桥引发的热量耗散问题。文章基于有限元分析等手段,通过通风条件及支承结构优化,解决了支承热桥引发的热量耗散问题。On the basis of experience from Fukushima accident,In-Vessel Retention(IVR)safety concept of 3rd generation nuclear power plant has been adopted in the nuclear island design of TNPS Project Unit 5&6,the Reactor Coolant Injection(RCI)system has been set.To realize the function of RCI system,a reliable passage with specified gap shall be maintained between Reactor Pressure Vessel(RPV),reactor pit wall and RPV thermal insulation,and this will cause heat dissipation problem due to insulation support thermal bridge.Based on finite element analysis,ventilation condition and support geometry has been improved to solve the heat dissipation problem.

关 键 词：堆腔冷却剂注入系统 反应堆压力容器保温层 堆坑壁混凝土温度限值 

分 类 号：TL42[核科学技术—核技术及应用]