先进堆非能动余热排出系统综合试验研究

介绍了先进堆非能动余热排出系统综合试验研究的试验装置和冷热芯位差阈值研究结果、稳态试验研究结果、瞬态特性分析结果,以及MISAP2.0程序改进、验证结果。试验研究结果可为先进压水堆核电站非能动余热排出系统原型设计(系统布置、设备容量和系统启动方式等)提供试验依据,并为舰船核动力装置非能动余热排出系统的研究与设计提供可参考的试验数据,开发的具有自主知识产权的MISAP2.0程序为我国自行设计先进堆非能动余热排出系统提供了必要的设计手段。

Experimental Research on Passive Residual Heat Removal System of Chinese Advanced PWR (In Chinese)

The secondary-side passive residual heat removal system (PRHRS) is considered in Chinese advanced PWR. Experimental research has been done in 2000 at advanced PWR PRHRS test facility which had been built according to scaling laws in Nuclear Power Institute of China, as well as the computer code MISAP2.0 has been developed and verified. More than 30 transient tests had been performed while the residual heat drops from 8% full power to 2% full power. And more than 280 sets of steady tests data have been employed to analyze the effect of the threshold of elevation between hot resource and hot sink and to verify the prediction of MISAP2.0. Based on the experiments, a semi-empirical model related to height between hot resource and hot sink has been established which can be applied to system arrangement design for PRHRS of Chinese advanced PWR. Transient experiment also provide basis for system(prototype) startup mode. Furthermore, a way to call off potential water hammer has been identified. Computer code MISAP2.0 has been developed with self-reliance copyright, which is a useful tool for design of PRHRS.