中国实验快堆负荷跟踪能力分析  

Analysis of Load-following Capacity of CEFR

作　　者：张玮瑛 段天英[1] 刘勇[1] 张厚明 肖志[3] 

机构地区：[1]中国原子能科学研究院反应堆工程技术研究部,北京102413 [2]国家核安全局华北核与辐射安全监督站,北京100191 [3]环境保护部核与辐射安全中心,北京100082

出　　处：《原子能科学技术》2017年第11期2028-2035,共8页Atomic Energy Science and Technology

摘　　要：以中国实验快堆(CEFR)主工艺系统为对象,利用MATLAB/Simulink软件建立仿真模型。在负荷阶跃变化且无调节系统参与的条件下进行仿真计算,研究CEFR及类似工艺的池式钠冷快堆的负荷跟踪能力。分析关键环节在负荷阶跃变化的极端情况下的运行特性,探究此类工艺负荷跟踪运行模式的可行性,为未来大型快堆在运行模式和工艺设计上提供参考。仿真结果表明,CEFR及其类似工艺的池式钠冷快堆负荷跟踪能力有限,其中直流式蒸汽发生器是限制其负荷跟踪能力的最大瓶颈。Taking the main process systems of China Experimental Fast Reactor （CEFR） as the research object, all the related simulation models were built on the MATLAB/Simulink platform. In research of the capabilities of the pool-type sodiumcooled fast breeder reactors like CEFR, the models under load step disturbances without exerting control systems were simulated. The dynamic characteristics of the key devices and systems were analyzed to explore the possibilities of the load-following operational mode, thus providing references for the design of future demonstration fast reactors. Simulation results show that the load-following capacity of CEFR is unsatisfactory, for which the once-through steam generator may be the choke point.

关 键 词：钠冷快堆 负荷跟踪 模型 仿真 MATLAB SIMULINK 

分 类 号：TL361[核科学技术—核技术及应用]