池式钠冷快堆事故余热排出系统一回路仿真研究

池式钠冷快堆事故余热排出系统采用了非能动工作原理,依靠液态钠及空气的自然对流排出堆芯余热。为研究事故工况下余热排出系统一回路的换热能力,基于FORTRAN语言,建立堆芯单通道及盒间流模型,采用全隐二阶迎风差分格式及改进的欧拉法离散求解,对事故余热排出系统一回路系统进行数值模拟,并对全厂断电事故进行仿真计算验证。结果表明:该程序能较好地反映事故余热排出系统瞬态变化过程,并可达到超实时仿真。

Simulation Research on Decay Heat Removal System in Primary Loop of Pool-type Sodium-cooled Fast Reactor

The decay heat removal system in pool-type sodium-cooled fast reactor (PSFR) is the passive safety system, which depends on the natural circulation of sodium and air to keep the reactor coolant cooled. In order to verify the characteristics of the heat transfer of decay heat removal system in primary loop for accident condition, the core single-channel model and the flow between fuel assemblies model were established to simulate the decay heat removal system of primary loop and testify the program on station blackout accident, by using fully-implicit second-order upwind scheme and ameliorative Eular method to solve the equations based on FORTRAN. The calculation results show that the program could reflect the transient characteristics of the decay heat removal system, and it could reach excess real-time simulation.