作　　者： ; ; ; ; ; ;

机构地区： 西安交通大学能源与动力工程学院动力工程多相流国家重点实验室

出　　处： 《动力工程》 2007年第2期223-226,共4页

摘　　要： 对CNP1000核反应堆冷却剂安全注入接管内射流的流动特性进行了可视化研究。在相同的流速比下,流型和射流穿透深度、影响区域基本相同;随着流速比的增加,射流穿透深度增大,偏斜减小,沿主管管壁流体减少。结果对于后续的传热试验热测点布置具有重要的指导意义。传热试验结果对反应堆安全注入接管的结构疲劳分析提供相关数据,并为反应堆结构设计提供依据。 Studies have been conducted on visualization of flow patterns in safety injector pipes, connecting the cooling system of nuclear reactor CNP-1000 with its main piping. Tests show that the flow pattern, the jet＇s depth of penetration and the extent of the affected region remain the same if the velocity ratio is kept constant; while increasing the velocity ratio causes the jet＇ s penetration depth to extend, flow deflection to diminish and flow along the manifold＇ s wall to reduce. Test results were a valuable guide for positioning temperature sensors in succeeding heat transfer tests, which served the purpose of providing data for structural fatigue safety analysis of the injector＇ s connection piping with the reactor, and thus may serve as basic reference material for the reactor＇s structural design. Figs 8 and refs 10.

关 键 词： 工程热物理 流动可视化 射流 流速比 穿透深度

领　　域： [核科学技术]