摘要
应用SimCont程序对AP1000核电厂非能动安全壳冷却系统进行仿真建模,并以主蒸汽管道破裂、冷却剂环路冷管段双端断裂等最严重的设计基准事故为研究对象,仿真分析非能动安全壳冷却系统的响应和主要设备的功能实现,对仿真程序进行综合评价。结果表明:SimCont程序仿真模型能很好地反映出非能动安全壳冷却系统的功能,计算结果与安全分析报告基本吻合。
The simulation of AP1000 passive containment cooling system based on SimCont was studied.The transient response of passive containment cooling system and the functional performances of the main equipments were simulated and the simulation tool was comprehensively assessed aiming at the main steam line break accident and the double-ended break of cold leg of coolant loop accident which were the most severe design basis accidents.The code＇s performance was estimated.The results show that the model of SimCont can well reflect the function of passive containment cooling system,and the calculation results are consistent with that in the safety analysis report.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2013年第5期794-797,共4页
Atomic Energy Science and Technology
基金
国家重大专项资助项目(2011ZX06004-008)
