压水堆核电厂一回路仿真可视化研究

Visualized Research on Primary Loop Simulation for PWR Nuclear Power Plant

  • 摘要: 对压水堆核电厂一回路系统及主要设备进行了详细分析,建立了点堆中子动力学模型、两相漂移流蒸汽发生器模型、三区不平衡稳压器模型和主循环泵四象限特性模型,并以此为基础使用FORTRAN90语言和Visual C++语言通过混合编程的方法开发了核电厂仿真分析程序,实现了对压水堆核电厂一回路主要设备及全系统的可视化仿真计算。软件提供实时绘图、缩放等可视化功能,还提供了数据结果的标准图片格式和标准文本格式输出。通过将程序的计算结果与RELAP5/MOD3.0计算结果进行比较,对程序的可靠性进行了验证。

     

    Abstract: In this study the main equipments and the primary loop of PWR nuclear power plant (NPP) were analyzed in detail. The model of point neutron dynamics, steam generator model with two phase drift flux governing equations, 3-zone non-equilibrium pressurizer model and 4-quadrant main pump performance model were established. Based on the above models, a NPP simulation program was developed by using mixed programming with FORTRAN90 and Visual C++. The simulation program is of capability to achieve visualized simulation for the main equipments in primary loop and entire system of PWR nuclear power plant. It provides not only the visualized functions of real-time plotting, zooming, etc., but also the output of numerical results with standard picture and/or text formatting files. Besides, the program was validated by comparing the calculation results of the program developed by authors and those of RELAP5/MOD3.0.

     

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