模块式小型堆非能动堆腔注水冷却堆芯的严重事故分析  

Severe Accident Analysis of Core Cooling by Passive Cavity Injection System for Small Modular Reactor

作　　者：毛辉辉[1] 陈树[1] 邓坚[1] 向清安 肖红 

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 [2]环境保护部核与辐射安全中心,中国北京100082

出　　处：《科技视界》2015年第20期5-6,100,共3页Science & Technology Vision

摘　　要：以模块式小型堆为研究对象,使用MELCOR程序建立了电厂模型。选取安注管线双端剪切断裂严重事故为保守事故序列,非能动堆腔注水系统(Passive Cavity Injection System,PCIS)投入后,分析堆芯热量通过吊篮和压力容器壁进入堆腔水的传热过程,并评价燃料棒结构状态。计算结果表明,堆芯支承板保持支撑燃料组件,堆芯大部分燃料组件包壳保持棒状结构状态,PCIS冷却压力容器外壁面带出堆芯热量实现堆芯冷却。The model of Small Modular Reactor is build using MELCOR code. This paper analyzes cure heat removed process through the wall of Reactor Pressure Vessel by Passive Cavity Injection System （PCIS）, by selecting DVI double-cut rupture as the conservative severe accident sequence, and determine the fuel rod state. The results showed that core support plate support the fuel assembly all the time, most fuel rod could remain standing, the core heat could be removed through the wall of Reactor Pressure Vessel by PCIS.

关 键 词：PCIS 堆芯冷却 MELCOR程序 

分 类 号：TL413.064[核科学技术—核技术及应用]