原子能科学技术2018，Vol.52Issue(6)：1013-1020,8.DOI:10.7538/yzk.2017.youxian.0564
钠冷快堆二回路系统热工水力瞬态分析程序SELTAC的开发与应用
Development and Application of Transient Analysis Code SELTAC for Secondary Loop of Sodium-cooled Fast Reactor
叶尚尚 1杨红义 1刘一哲 1王晓坤 1杨晓燕 1杨军 1王利霞1
作者信息
- 1. 中国原子能科学研究院 反应堆工程技术研究部,北京 102413
- 折叠
摘要
Abstract
A thermal-hydraulic microcomputer code SEL T AC(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 shut-down 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 devia-tion is no more than 4.34％,and the coincidence degree is better.An emergency shut-down 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 loop provide a reference for the design of large commercial SFR.关键词
钠冷快堆/二回路系统/热工水力/瞬态分析程序/SELTACKey words
sodium-cooled fast reactor/secondary loop/thermal-hydraulics/transient analysis code/SELTAC分类
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叶尚尚,杨红义,刘一哲,王晓坤,杨晓燕,杨军,王利霞..钠冷快堆二回路系统热工水力瞬态分析程序SELTAC的开发与应用[J].原子能科学技术,2018,52(6):1013-1020,8.
