摘要
利用三代核电非能动余热排出实验装置(ESPRIT),开展了华龙1号非能动余热排出系统(PRS)自然循环特性实验。对PRS系统稳态特性实验研究和72 h长期自然循环特性的实验装置、实验工况和实验结果进行了介绍。实验结果表明,PRS系统和冷却器0.5%FP的设计能力是可以达到的,且系统还具有稳定带出0.8%FP堆芯热量的能力,PRS系统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。
Experiments on the natural circulation performance of the secondary passive residual heat removal system (PRS) for Hua Long Yi Hao have been performed by using the high temperature high pressure thermal-hydraulic test facility ESPRIT (Emergency Secondary Passive Residual Heat Removal System Integral Test Facility). The experimental results show that the heat transfer of PRS and the condensation heat exchanger meet the design parameters of 0.5%FP. The result also shows that the core heat can be sufficiently removed during 72h after shutdown in station black-out (SBO) accident.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2015年第4期1-3,共3页
Nuclear Power Engineering