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Experimental study of hydrodynamics and heat transfer in two-phase natural circulation loop with reference passive cooling systems of nuclear power plants

机译:核电厂参考无源冷却系统的两相自然循环回路中流体动力学和传热的实验研究

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In spite of long year practical use of natural circulation systems and not less long period of study working characteristics of these systems the problem of reliable predicting calculations of natural circulation loops (NCL) with boiling coolant at low reduced pressures is not likely can be considered as being solved. At the same time the interest to solution of this problem arises today, because low pressure natural circulation loops are considered as main type of post accident passive cooling systems for nuclear power plants. The main difficulties for calculations are concerned with determining friction pressure losses, which are strongly depended on two-phase flow pattern. At low reduced pressures large difference between liquid and vapour (gas) specific volumes predetermines the strong change of flow pattern even at small change of mass flow quality. An attempts to calculate local two-phase flow parameters (void fraction, circulation velocity) in the wide range of mass flow qualities without considering the change of flow patterns often lead to large deviations of calculated values from the results of experimental measurements. Another specific feature of two-phase low pressure NCL is hydrodynamic flow instability with circulation velocity pulsations of high amplitude and the occurrence of reverse flows. This also presents problems in developing calculation method. In present paper a method for calculating a low-pressure NCL has been developed, in which local two-phase flow parameters (void fraction, the phases velocities, pressure) are calculated using a modified homogeneous model with taking into account the distribution factor and the phases slip and a model of an annular-dispersed flow with considering droplets entrainment and deposition. A modified homogeneous model was applied for description quasihomogeneous flow regimes. At high values of void fraction annular-dispersed flow model was used. Recommendations for change from one model to another in practical calculations have been formulated and verified. The proposed calculation method has been verified by the comparison the calculated thermo-hydraulic characteristics of laboratory natural circulation loop with the experimental data. The experiments have been carried out for boiling in the loop of three different liquids - water, ethanol and perfluorohexane (FC-72) at atmospheric pressure. The comparison of calculated and experimental results showed their good agreement.
机译:尽管很长一年的实际使用自然循环系统,但这些系统的研究工作特征不太较长,但在低降低压力下,用沸腾冷却剂可靠地预测自然循环环(NCL)的问题不太可能被视为解决。同时,今天出现了解决这个问题的解决问题,因为低压自然循环环被认为是核电站后事故后无源冷却系统的主要类型。计算的主要困难涉及确定摩擦压力损失,这些压力损失强烈地依赖于两相流动模式。在低降低压力下,液体和蒸气(气体)特异性体积的大差异使得即使在较小的质量流量质量的情况下也能够预先确定流动模式的强大变化。在不考虑流动模式的变化的情况下,试图在广泛的质量流量质量中计算局部两相流量参数(空隙分数,循环速度),而不考虑流动模式的变化通常导致计算值从实验测量结果中的计算值大的偏差。两相低压NCL的另一个特定特征是具有高振幅的循环速度脉动和反向流动的流体动力流动不稳定性。这也提出了开发计算方法的问题。在本文中,已经开发了一种用于计算低压NCL的方法,其中使用改进的均匀模型计算局部两相流程(空隙率,相速度,压力),同时考虑到分布因子和考虑液滴夹带和沉积,阶段滑动和环形分散流的模型。应用修改的均匀模型,用于描述QuasihomeneOce流量制度。在使用空隙级分的高值下,使用了环形分散的流动模型。制定并验证了在实际计算中从一个模型转换到另一个模型的建议。通过对实验数据的实验室自然循环回路的计算的热液压特性进行了验证了所提出的计算方法。在大气压下,已经在三种不同液体 - 水,乙醇和全氟己烷(Fc-72)的环中煮沸的实验。计算和实验结果的比较显示了他们的良好一致性。

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