非能动安全壳冷却系统热工水力单项试验  

Thermal-hydraulic Tests on Passive Containment Cooling System of Advanced PWR

作　　者：谭曙时[1] 冷贵君[1] 程旭 倪永君[1] 

机构地区：[1]中国核动力研究设计院,成都610041 [2]德国卡尔斯鲁厄研究中心,3640d76021

出　　处：《核动力工程》2002年第A02期30-33,共4页Nuclear Power Engineering

摘　　要：非能动安全壳冷却系统热工水力单项试验研究项目。本试验利用德国Karlsruhe研究中心的PASCO试验装置,并对其进行改造,主要研究事故工况下非能动安全壳环形空腔内传热传质机理,包括干平板传热试验、加热平板蒸发传热试验、辐射传热试验,从而获得不同温度、环腔尺寸、表面黑度、喷淋流量对流动及传热的影响,验证相关模型及为设计提供参考。Thermal-hydraulic tests on the passive containment cooling system performed at the modified PASCO test facility is a key project of the advanced PWR. It includes heat transfer tests under dry conditions , wet conditions and radiating tests. The effect of the temperature, channel dimension, wall emissivity water film flow are discussed in the tests. The experimental data can be used to verify the models in computer codes and to give a reference for designing PCCS, and improve the understanding of passive safety features involved in PCCS.

关 键 词：热工水力单项试验 非能动安全壳 冷却系统 先进压水堆 传热 传质 

分 类 号：TL353.1[核科学技术—核技术及应用] TL421.1