【摘要】 针对核电站小破口失水事故,对锐边直管长径比L/D从1.01到25.61的5种破口型式进行了试验研究,其滞止压力从4.0MPa到22.0MPa,入口流体为饱和及过冷水,过冷度从0℃到60℃。采用均相热力学非平衡模型给出了临界流计算方法,根据试验数据给出了临界流压力比及热不平衡数与长径比L/D的关联式。所得临界流的预报值与试验结果符合良好,用于反应堆安全分析计算,可获得更精确的结果。更多还原

【Abstract】 Under the conditions of small break loss-of-coolant accident of nuclear power stations, the transient critical flow experiments for 5 sharp-edged tubes with L/D from 1.01 to 25.61 as the break geometries were conducted. The initial pressures were from 4.0 MPa to 22.0 MPa, and the subcoolings of the fluid were from 0℃to 60℃. An correlation was established to predict the critical flow rates by using the thermal nonequilibrium homogeneous model. Based on the data of tests the critical flow pressure ratio and the thermal nonequilibrium number were correlated as the function of the tube length to tube diameter ratio L/D. The predicted critical flow rate has a good agreement with experimental data, so it may be used to the safety analysis of nuclear power station.更多还原