二次侧非能动余热排出系统特性参数影响因素实验研究

Experimental Research on the Parameter Affecting on the Characteristics of Secondary Side Residual Heat Removal System

利用三代核电非能动余热排出实验装置(ESPRIT),针对中核集团自主研发的三代核电华龙1号(ACP1000),开展了华龙1号非能动余热排出系统(PRS)特性参数影响因素实验研究。本文对实验装置、实验工况和实验结果进行了介绍。实验结果表明:系统阻力实验参数范围内,PRS均能够在无人员干预的条件下安全带出全厂断电事故发生后72 h堆芯热量;40%~160%额定换热面积范围内冷却器和单个系列PRS均具有稳定带出0.8%FP(满功率)堆芯热量的能力;实验范围内蒸汽发生器(SG)水位对同一功率稳定后压力和蒸汽温度的影响并不显著。

The experimental research has been carried out to investigate the effect of parameters on the characteristics of the secondary side residual heat removal system in for Hua Long Yi Hao using the Emergency Secondary Passive Residual heat removal system Integral Test facility （ESPRIT）. The ESPRIT test facility, experimental working conditions and results are presented in this paper. The experimental results reveal that the PRS is capable of removing the core residual heat in station blackout scenario without staff intervention in 72 hours. The 0.8%FP core heat can be removed with the single PRS series or under the 40%-160% heat exchanger heat transfer area. The liquid level in the steam generator has no significant effect on the system pressure and steam temperature.