高性能轻水堆中子物理-热工水力耦合行为分析

Neutronic/Thermo-hydraulic Coupling Behavior Analysis of HPLWR

  • 摘要: 针对1种典型的“三流程”超临界水堆——高性能轻水堆(HPLWR)开发了中子物理热工水力耦合分析程序,并对其堆芯进行了核热耦合计算。基于该程序开展了传热关系式敏感性研究,得出适用于HPLWR核热耦合的传热关系式,进而对HPLWR进行中子物理-热工水力耦合行为计算,得出了一些关键参数沿轴向的分布规律。结果表明:开发的程序可较好地分析高性能轻水堆的中子物理热工水力耦合行为。

     

    Abstract: A code to analyze the neutronic/thermo-hydraulic coupling effect was developed for the high performance light water reactor (HPLWR), which is a typical “three pass core” SCWR. Based on this code, a sensitivity study of different heat transfer correlations was performed on the neutronic/thermal-hydraulic coupling characteristics of HPLWR. Furthermore, the key parameters of HPLWR were investigated using the developed code. The results show that the developed code can be efficiently used to analyze the neutronic/thermo-hydraulic coupling behavior of HPLWR.

     

/

返回文章
返回