池式钠冷快堆系统分析程序开发

针对池式钠冷快堆的特点，在对快堆系统的水力模型、热工模型和中子动力学模型进行详细分类和建模的基础上，利用FORTRAN95语言开发了可用于池式钠冷快堆事故分析的系统分析程序（FASYS程序）。以中国实验快堆为计算对象对FASYS程序模型进行了初步验证，所获得的结果和试验值与其他系统程序计算值符合良好，证明了所开发的系统分析程序的正确性。

Development of Pool-type Sodium-cooled Fast Reactor System Analysis Code

According to the characteristics of pool‐type sodium‐cooled fast reactor ,and with the fast reactor hydraulic model , thermal model and neutron kinetics model thoroughly classified and developed ,a fast reactor system analysis code (FASYS code) was developed by FORTRAN95 language for pool‐type sodium‐cooled fast reactor acci‐dent analysis .Transient conditions in CEFR were calculated with FASYS code and the results were used for code validation .The calculation results are consistent with the test data and other fast reactor system analysis code results , and the correctness of the FASYS code is proved .