摘要
以中国改进型压水堆核电站CPR1000为研究对象,在其蒸汽发生器(SG)二次侧设计了1套非能动排热系统。为验证该系统在主给水管道破裂(MFLB)事故下的热量排出能力,采用RELAP5/MOD3.2程序对系统进行合理的简化并建模。结果表明:MFLB事故发生后,系统内可迅速建立起自然循环流动;该系统的及时投入可使一回路温度和压力的上升得到有效缓解,在隔离受影响的SG之前,一回路未出现整体沸腾,稳压器未满溢,保证了堆芯和一回路冷却剂系统的完整性。
A new secondary passive heat removal system was designed for CPR1000.In order to verify the capability of removing heat for the system under the major feedwater line break（MFLB） accident,the model of the simplified system for CPR1000 was established by using RELAP5/MOD3.2 code.The calculation results show that natural circulation in passive heat removal system is quickly established,and the increasing of temperature and pressure in the primary loop is mitigated due to the timely input of passive heat removal system.There is no bulk boiling in the primary loop and the pressurizer does not overflow before the operator isolates the affected steam generator,which assures the integrity of the core and the main coolant system.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2012年第12期1434-1439,共6页
Atomic Energy Science and Technology
基金
核能开发项目资助(科工二司[2008]700号)
