The nuclear power plant simulator for high temperature gas-cooled reactor (HTR) is under construction for the training and certification of the operators. The thermal hydraulic model was established in real time calculation by flow network and heat transfer network according to the core structure. In the core model, the effect of cross flow and heat transfer on the flow and temperature distributions were discussed in the normal operation and pressurized loss of forced cooling accident (PLOFC). The results indicated that the flow and heat transfer performance is not sensitive to the cross flow and heat transfer in the normal operation condition. While in the PLOFC, the cross flow and heat transfer in the reactor core is important in forming the natural circulation, removing the decay heat, as well as the transients of the flow and temperature distributions. By adding cross flow and heat transfer, the thermal states of the reactor core in the PLOFC agree well with the results by the system code. To fulfill the fidelity and scope of the HTR simulator, cross flow and heat transfer should be considered in therncore model.%为完成核电厂操纵员的培训和考试,需开展适用于高温气冷堆的模拟机研究.根据球床堆芯的特点,利用流体网络与传热网络建立了可实时计算的热工水力模型,讨论了球床中氦气沿径向的流动及换热对堆芯热工水力性能的影响.结果表明,在正常运行工况下,径向流动与换热对轴向流动的影响较小,模拟结果差别不大；而在失流不失压工况下,径向流动与换热对堆芯自然对流的形成、余热导出及整个瞬态过程的影响均较为明显,考虑径向流动与换热的仿真结果与设计软件的结果符合更好.考虑到模拟机仿真范围和逼真度的要求,在高温堆模拟机堆芯建模中需加入径向流动及换热模块.
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