摘要
针对钠冷快堆二回路系统的具体结构和运行特点,对中间热交换器、直流蒸汽发生器、钠缓冲罐以及泵、管道等设备和部件建立模型,采用FORTRAN语言自主编制了二回路系统热工水力瞬态分析程序SELTAC。利用中国实验快堆的停堆试验数据对所编制程序进行了初步验证。结果表明,程序计算值与试验值趋势一致,最大相对偏差不超过4.34%,吻合程度较好。将验证后的程序与一回路系统程序耦合,分析了某600 MW钠冷快堆在主热传输系统保持排热能力时的紧急停堆工况,得到了二回路系统的瞬态特性,为大型商用快堆电站的设计提供了参考。
A thermal-hydraulic microcomputer code SELTAC（secondary loop transient analysis code）for transient analysis for secondary loop of pool type sodium-cooled fast reactor（SFR）was developed using FORTRAN language.In the SELTAC,the model of IHX（intermediate heat exchanger）,OTSG（once-through steam generator）,SBT（sodium buffer tank）,and pump was established.The code was verified by the shutdown transient test data of CEFR（China Experimental Fast Reactor）.The results show that the calculated value is consistent with the test value,the maximum relative deviation is no more than 4.34%,and the coincidence degree is better.An emergency shutdown accident was analyzed for a 600 MW SFR based on the combined code between SELTAC and primary loop transient analysis code,when the main heat transfer system was normal.The thermal-hydraulic transient characteristics of the secondary loopprovide a reference for the design of large commercial SFR.
作者
叶尚尚
杨红义
刘一哲
王晓坤
杨晓燕
杨军
王利霞
YE Shangshang,YANG Hongyi,LIU Yizhe,WANG Xiaokun,YANG Xiaoyan,YANG Jun,WANG Lixia(China Institute of Atomic Energy, P. O. Box 275-34, Beijing 102413, Chin)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2018年第6期1013-1020,共8页
Atomic Energy Science and Technology
