摘要
针对核电厂反应堆水力学分析的需求,中国核动力研究设计院自主研发了PHYCA软件。为了迚一步评价软件的工程适用性,以自主化三代核电"华龙一号"为对象,开展了基于PHYCA软件的反应堆水力学分析,给出了压力容器内主要部件的压降、压力容器内各类旁流量和堆内构件水力载荷,其值与工程设计结果相近,表明PHYCA软件可用于类似核电厂的反应堆水力学分析。
For the requirements of the reactor hydraulic analysis, the PHYCA program has been developed by Nuclear Power Institute of China on self-reliance. In order to evaluate its engineering adaptability, the analysis of the reactor hydraulics of HPR1000 was performed based on PHYCA. Pressure drop in the reactor vessel, bypass flow and hydraulic load of the reactor internals were calculated. The results of PHYCA have good agreement with the engineering design values. It demonstrates that PHYCA is suitable for the analysis of the reactor hydraulics of similar nuclear power plants.
引文
[1]黄慧剑,刘余,潘俊杰,等.水力学分析软件PHYCA的研发[J].中国核电,2015, 8(s2):1163-1167.
[2]李经纬.秦山核电二期工程反应堆热工水力设计[J].核动力工程,1999, 20(4):308-312.