竖直圆管内空泡份额径向分布特性形成机制

在常温常压下,采用光纤探针测量方法对垂直上升大圆管中空气-水两相流动的空泡份额径向分布特性及形成机制进行研究。实验选用圆管直径为100 mm,气相、液相折算速度的范围分别为0.004~0.053 m/s和0.071~0.213 m/s。结果表明空泡份额径向分布随着气-液流量的不同,呈现出"核峰"或"壁峰"型分布特点;通过分析气泡所受到的横向升力和壁面力,表明二者对气泡横向运动的综合作用是造成空泡份额径向分布呈现出"核峰"或"壁峰"型分布的主要原因。     

竖直下降两相流相界面结构输运特性

竖直下降两相流具有与竖直上升两相流不同的相界面结构特征及输运特性。本文对竖直下降管内的气水两相流进行了实验研究,运用微型四头电导探针对7.5、31.5及55.5倍管径横截面处的空泡份额、相界面浓度、气泡直径、气泡频率及气泡速度等相界面结构参数的局部分布进行了测量。分析获得了相界面结构参数的沿程变化规律,并研究了气相表观流速对相界面结构发展的影响及一维相界面结构输运特性。发现竖直下降泡状流的升力指向管中心,导致相界面结构参数基本呈中心峰值分布;气相表观流速的增大会提高空泡份额和相界面浓度分布的峰度;竖直下降两相流在距入口31.5倍管径处基本达到充分发展。     

环形流道两相流特性实验研究

在日本原子力研究所的一个两以试验台架上,进行了环形流道空气－水丙相流窟泡份额和逆向流试验,观察了其流型。通过试验和分析,提出了漂移流模型中分布系数Co和气相漂移速度Vgi的经验关系式;得到了逆向流Wallis表达式的拟合参数。对试验结果的分析表明,当流道间隙很小（Bond数小于1）时,流型和两相流动与间隙较大时有所不同。     

竖直圆管内泡状流空泡份额径向分布实验研究

常温常压下,采用光学探针测量方法,对圆管（内径50 mm）内空气 水两相竖直向上泡状流空泡份额的径向分布特性进行了实验研究。结果表明,竖直圆管内泡状流空泡份额的径向分布随气液两相表观流速不同而变化。液相流速较高时空泡份额分布呈“壁峰型”,即中心区域变化平缓,近壁区出现峰值后迅速降低;液相静止时,随气相流速增加,空泡份额增加速度沿径向向外逐渐减小,气相流速较大时分布呈“核峰型”,即空泡份额随径向位置向外呈减小趋势;液相流速较低时分布呈现出过渡型。探针测量面积加权平均空泡份额与通过重位压降得到的空泡份额的相对偏差小于10%。     

垂直上升横掠水平管束的两相流空泡份额模型研究

与管内两相流空泡份额模型相比,垂直上升横掠水平管束的两相流空泡份额研究成果相对有限。利用垂直上升的气-水两相流横掠水平管束的实验数据,对现有的空泡份额计算模型进行对比分析,并对2种现有模型的拟合公式进行修正。采用其他实验结果对本文重新修正的空泡份额模型进行验证,结果表明:与原始模型相比,修正的空泡份额计算模型给出的空泡份额预测值更好。     

管束间空气-水两相流激振力特性及归一化方法研究

利用管束间空气-水两相流激振力的实验数据,研究了两相流激振力的部分特性,分析了混合物流速、空泡特征长度等两相流参数对两相流激振力的影响。结果表明,两相流激振力约与界面流速、混合物密度和混合物运动黏度呈正比,泡状流下激振力随气泡直径线性增长,证明两相流激振力的无量纲归一化可采用气泡数率作为频率缩比参数。基于上述两相流激振力的特性,从方便工程应用角度给出了两相流激振力的无量纲归一化方法,获得了较好的归一化效果。     

ERVC流道内两相局部分布实验研究

采用1∶1循环高度的切片实验装置模拟压力容器外部冷却流道,通过向实验段注入空气模拟压力容器外部两相自然循环过程,采用自制电导探针对系统内的局部空泡份额分布进行实验测量和分析。实验结果表明:压力容器外部冷却流道内的两相流具有显著的局部分布特征,流道截面上的局部空泡份额类型从壁面峰值分布类型过渡到近壁面峰值分布类型,最终发展成为中心分布类型;液相和气相流量的敏感性分析表明,气相流量的大小对局部空泡份额分布特征有较大的影响。     

基于漂移流模型的矩形通道内泡状流-弹状流转变准则

以空气和水为工质,对竖直向上矩形通道(40 mm×1.41 mm,40 mm×10 mm)两相流流型特性进行了可视化研究。气液相表观速度分别为0.01~0.59 m/s和0.02~3.72 m/s。基于3个经典的泡状流向弹状流转变准则,考虑矩形通道的尺寸效应,导出了泡状流向弹状流转变时的临界空泡份额为0.23。以窄边宽度2.5 mm为界,将矩形通道分为小通道和常规通道两类,对泡状流向弹状流转变准则进行修正,修正准则能很好地预测实验值。为进一步验证修正准则的准确性和适用性,将修正准则与Mishima、Wilmarth和Sadatomi等的实验数据进行了对比,结果显示修正准则同样具有较好的预测效果。     

竖直窄矩形通道内空气-水两相流中气弹运动速度研究

以空气和水为工质,应用高速摄像仪,对竖直窄矩形通道(3.25 mm×40 mm)内气液两相弹状流进行了可视化实验研究。气、液相表观速度分别为0.1~2.51 m/s和0.16~2.62 m/s,工作压力为常压。实验中发现窄矩形通道内弹状流与圆管中存在较大差别,气弹多发生变形,高液相流速时变形更为严重。窄边液膜含气量较高,在高液相流速时窄边液膜不下落,宽边液膜中含有由气弹头部进入和气弹尾部进入的气泡。气弹速度受气弹头部形状和宽度影响较大,受气弹长度影响较小。气弹速度可由Ishii & Jones-Zuber模型计算,但在低液相折算速度时偏差较大,其主要原因为漂移速度计算值较实验值偏小。     

竖直管内两相流逆向流动特性研究

实验发现在竖直管内两相流逆向流动过程中,由于气体的入口条件不同、淹没开始点可能出现在气相的入口处,也可能出现在出口处。由于出现的位置不同,淹没开始点所对应的气、水之间的关系式也不一样。这一实验结果对进一步研究淹没开始的机理有重要意义。根据两相流的流动特性,分析了出现这种现象的原因,提出应采用不同的关系式计算这 两种不同的淹没开始点。     

竖直大圆管内两相流动界面输运过程研究

采用光纤探针测量方法研究了垂直上升管中空气-水两相流动的局部界面面积浓度（IAC）和空泡份额等分布规律。实验选用的圆管直径为100 mm,气相、液相表观速度的范围分别为0～0.1 m/s和0～1.0 m/s。结果发现,影响径向IAC分布的因素主要为气泡通过频率。基于Ishii-Kim界面输运模型,对轴向IAC进行了计算;通过分析4种气泡间相互作用对IAC的影响,发现工作压力是影响轴向IAC变化的主要因素,最后给出了引入工作压力影响的轴向IAC计算关联式。     

管内向下气液两相流动界面参数分布特性

借助双探头光纤探针测量方法,对管内竖直向下空气-水两相流动的界面参数局部分布特性进行了实验研究。实验段采用内径50 mm、长度2 000 mm的圆管,气液两相表观速度范围分别为0.004～0.077 m/s和0.43～0.71 m/s。实验结果表明,不同于竖直向上两相流动中局部界面参数径向分布呈现的“壁峰”或“核峰”型分布,向下流动中局部界面参数径向分布呈“壁峰”或“宽峰”型分布;向下流动时空泡份额截面平均值均比向上流动时大119.6%～145.0%,界面面积浓度截面平均值比向上流动时大18.8%～82.5%;向下流动时界面参数分布表现出明显的均匀化趋势。     

窄矩形通道内搅混流和环状流相界面参数的计算方法

空泡份额和界面浓度是两相流动中重要的相界面参数,准确获取窄矩形通道内搅混流和环状流工况下空泡份额和界面浓度是构建和完善两流体模型的关键。本文针对横截面为65 mm×2 mm的矩形通道开展了气液两相流动特性可视化实验研究,气相折算速度j_g＝1～9 m/s,液相折算速度j_f＝0.1～1.5 m/s,流型包含搅混流和环状流。提出了基于高速摄像法获取搅混流和环状流下空泡份额和界面浓度的分析计算方法,利用该方法所得空泡份额与窄矩形通道内经验关系式计算值的相对偏差约在10%以内。此计算方法可为研究复杂流型下窄矩形通道内的相界面参数提供理论依据。     

起伏振动状态下倾斜管气液两相流型实验研究

在起伏振动状态下对倾斜管内气液两相流进行了实验研究。将振动装置与两相流实验回路相结合,改变管道倾角和振动频率、振幅,分析其对流型转变的影响。研究发现振动条件下的流型与稳态下相比有较大区别,通过对流型分类发现两种新流型为珠状流、起伏弹状流。绘制流型转换边界图结果表明,倾角的增加使起伏弹状流在流型图中的区域扩张,其他流型的区域相对减小。振动频率和振幅对流型转换边界的影响相似,振动频率和振幅增加会使珠状流和准弹状流区域有所增加。3种变化因素中振动频率对流型转变的影响最大。     

New Interfacial Drag Force Model Including Effect of Bubble Wake, (I) Model Development for Steam-Water Bubbly Flow in Large-Diameter Pipes

Several experimental results show that bubbles can easily be captured in the wake formed by leading bubbles when multiple bubbles are rising in a liquid. It is suggested from this experimental result that the effect of bubble wake should be included in the constitutive relationships representing the interfacial drag force. In the present study, steam-water bubbly flow experiments were performed to develop a new interfacial drag force model including the effect of bubble wake. Since the validity of the existing constitutive equations have been tested mainly for two-phase flow in small-diameter pipes, our study focused on two-phase flow in a large-diameter pipe. Using a one-dimensional two-fluid model, the applicability of the new interfacial drag force model to our experimental conditions was investigated. As a result, it was shown that the present model markedly improves the accuracy of the predicted results. It was therefore demonstrated that the present bubble wake model is effective at least for the conditions which were used for model development. Its applicability to different conditions will be discussed in a subsequent study.     

New Interfacial Drag Force Model Including Effect of Bubble Wake, (II)

In the previous study, we proposed a new interfacial drag force model based on experimental data of steam-water bubbly flow in a large-diameter pipe. This is because our experimental results had suggested that effect of bubble wake should be included in the interfacial drag force model, although it had not been taken into account in the existing models. A preliminary method for including the effect of bubble wake was hence developed and used in the new model. A new bubble size prediction method was also adopted in the model. In the present study, after improving the measuring equipment and signal processing procedure, another series of experiments was carried out. Using the new experimental data, the methods of predicting bubble size and effect of bubble wake were slightly modified. To test the validity of the new model, predicted results were compared with available experimental data sets of steam-water bubbly two-phase flow in large-diameter pipes. One-dimensional and two-dimensional two-fluid models were used for the calculation. Comparisons showed that the new model is in good agreement with the experimental data, whereas the model which does not take into account the effect of bubble wake overestimated the void fractions.     

Code performance with improved two-group interfacial area concentration correlation for one-dimensional forced convective two-phase flow simulation

In gas–liquid two-phase flow simulation for reactor safety analysis, interfacial momentum transfer in two-fluid model plays an important role in predicting void fraction. Depending on flow conditions, a shape of the two-phase interface complicatedly evolves. One of the proposed approaches is to quantify the gas–liquid interface information using interfacial area transport equation. On the other hand, a more simplified and robust approach is to classify bubbles into two-groups based on their transport characteristics and utilize constitutive equations for interfacial area concentration for each group. In this paper, interfacial drag model based on the two-group interfacial area concentration correlations is implemented into system analysis code, and void fractions were calculated for the evaluation of numerical behaviors. The present analysis includes (1) comparison of one-group and two-group relative velocity models, (2) comparison with separate effect test database, (3) uncertainty evaluation of drag coefficient, (4) numerical stability assessment in flow regime transition, and (5) transient analysis for simulating the prototypic condition. Results showed that utilization of interfacial drag force term using constitutive equations of two-group interfacial area concentration yields satisfactory void fraction calculation results. The proposed solution technique is practical and advantageous in view of reducing the computational cost and simplifying the solution scheme.     

矩形通道内气水两相流摩擦阻力计算模型

常压下以空气和去离子水为工质,对横截面为1.41 mm×40 mm和3 mm×40 mm的竖直矩形通道内两相流动阻力特性进行了实验研究。利用获得的764组实验数据,对11种典型两相流摩擦阻力计算模型进行评价。结果表明：Lee-Lee模型整体预测精度最高,但在分液相雷诺数较小（Re_l<600）和较大（Re_l>8 700）区域,与实验值符合较差;在分液相紊流区(Re_l≥2 000) Chisholm B模型适用性较好,对于两实验段预测值与实验值绝对平均误差分别为6.13%和6.43%,但在分液相层流区(Re_l<2 000)其预测值与实验值偏差较大。根据压降特性提出修正两相动力黏度,并针对分液相层流区提出修正计算关系式,其预测值与实验值符合较好。