压水堆核电站堆芯物理/热工水力耦合特性研究

采用RELAP5-HD作为堆芯耦合计算程序，以秦山核电二期工程反应堆堆芯为研究对象，建立堆芯活性区的物理/热工水力耦合模型，在此基础上进行了稳态计算和掉棒事故仿真研究。结果表明，使用RELAP5-HD计算得到的结果与电厂实测值符合较好，获得的掉棒事故参数曲线能准确反映事故工况下的参数变化趋势。稳态和事故工况的计算结果均符合堆芯物理/热工水力反馈效应的理论分析，证实了所建立的堆芯耦合模型的准确性，为下一步进行核电站系统的仿真分析提供基础。

Investigation on Coupling Characteristics of Neutronics/Thermal-hydraulics of PWR NPP Core

In this paper, an integrated neutronics/thermal-hydraulic model for the reactor of Qinshan Phase Ⅱ NPP project was developed, using the RELAP5-HD as core coupled computational code. Based on the coupled model, the steady state calculation and the rod drop transient simulation were performed. The results show that the values obtained from RELAP5-HD calculation agree well with the available measured data, and the calculated accident curves can predict all major parameters trends of the transient with good accuracy. Both steady state and transient calculation results are in accordance with the theoretical analysis from the feedback aspect of coupled reactor neutronics/thermal-hydraulics, this demonstrates that a successful coupled model of Qinshan Phase Ⅱ NPP core has been developed, and the established model provides a good foundation for further simulation analysis of the nuclear power plant system.