基于喷嘴临界流实验对现有物理模型的评价  

Evaluation of Existing Physical Models on Critical Flow Based on Experiment With a Nozzle

作　　者：陈玉宙[1] 杨春生[1] 张曙明[1] 赵民富[1] 杜开文[1] 毕可明[1] 

机构地区：[1]中国原子能科学研究院反应堆工程研究设计所,北京102413

出　　处：《原子能科学技术》2009年第6期485-490,共6页Atomic Energy Science and Technology

基　　金：国家重点基础研究发展计划资助项目(2007CB209800);IAEA协调研究计划资助项目(14469/R0)

摘　　要：以水为工质、直径1.41 mm的喷嘴为实验段,在稳态条件下进行临界流实验,覆盖的参数范围为：进口压力,0.4-22 MPa;进口温度,40-371℃;进口含汽率,-3.5-0.98。结果分析表明：在欠热度高于一定值下流动未达到临界条件;在低欠热度和低含汽率区域两相间存在热力不平衡性,在较低压力下,它对临界流率的影响十分显著。将实验数据与均匀平衡模型、Moody模型、Henry-Fauske模型、Burnell模型以及Bernoulli公式的计算结果进行比较,显示了各模型在不同条件下的适应性。A critical flow experiment of water was carried out at steady-state in a nozzle with diameter of 1.41 ram, covering the ranges of inlet pressure of 0. 4-22 MPa, inlet temperature of 40-371 ℃ and inlet quality of --3. 5-0. 98. The flow doesn＇t exhibit choking behavior at the inlet subcooling larger than a certain value. In low subcooling and low quality region thermal non-equilibrium between two phases has appreciable effect on the critical flow rate, especially at lower pressure. The experimental data were compared with the predictions of several models, including the Homogeneous equilibrium model, the Moody model, the Henry-Fauske model, the Burnell model and the Bernoulli correlation, showing their applicability for different conditions.

关 键 词：临界流 壅塞流动 热力非平衡 反应堆安全 破口事故 

分 类 号：TL33[核科学技术—核技术及应用]