气-液两相临界流速及压力扰动传播规律

应用整体平均两流体模型建立了带相变的气-液两相流压力波传播模型。根据小扰动原理和一阶线性齐次方程组有解的条件导出了两相压力波的色散方程。通过理论及实验数据分析了两相临界流速和压力脉冲及压力波传播速度间的关系,并研究了泡状流和弹状流流型下气-液两相压力波的传播规律。研究结果表明:气-液两相压力波具有色散特性,当扰动频率趋于∞时压力波传播速度等同于压力脉冲传播速度;两相临界流速与压力脉冲扰动传播速度相等价。     

外加扰动下垂直管内气-液两相流空隙波特性

采用双环电导探针技术实验研究了外加扰动对垂直上升管内气-液两相流空隙波特征的影响。研究结果表明,气-液两相流空隙波对外加周期性扰动具有频率选择性。在泡状流区,低频扰动能诱发与扰动等频的空隙波;在泡状流／弹状流转变区,低频扰动能加速气泡合并,促进泡状流向弹状流转变;而在弹状流区空隙波特征对外界扰动并不敏感。空隙波的传播速度受外界扰动频率的影响,随着扰动频率的增大,空隙波波速先减少又增大。本文的实验研究发现,存在对气-液两相流空隙波特征影响最为显著的临界扰动频率,在本实验条件和参数范围内,该临界扰动频率为20Hz。     

振动工况下环管内气液两相流参数分布实验研究

为模拟地震对反应堆堆芯内两相流动的影响,将振动产生装置与实验段结合,并利用电导探针技术实验研究了振动工况下环管内气液两相流局部参数的分布特性。振动装置所采用的偏心轮的偏心距为15.875mm,并可通过调节电机转速获得不同的振动周期。环管实验段内径和外径分别为19.1mm和38.1mm,总长度为2.32m。实验以空气和水为工质,流动工况覆盖了泡状流、弹状流及搅混流等流型。实验结果表明,振动对管内气液两相流局部参数如含气率和界面浓度等分布具有重要影响。随振动周期的减小,管内两相流参数分布发生明显变化。另外振动对低含气率的泡状流影响较大,随含气率的增加,流型逐渐向搅混流过度,振动对两相流参数的影响逐渐减小。     

铅铋合金冷却反应堆内气泡提升泵提升自然循环能力的理论研究

液态金属冷却核反应堆采用气泡提升泵的概念设计来提升堆芯自然循环能力。液态金属和惰性气体两相流动特性显著影响自然循环能力和系统安全性。本工作对铅铋合金冷却反应堆中气泡提升泵提升自然循环能力进行数值模拟研究。基于漂移流模型,采用空泡份额预测模型和摩擦压降预测模型分析了气体质量流量、质量含气率、气泡直径、上升管道高度对气泡提升泵提升自然循环能力的影响。结果表明：泡状流区域中,对于给定的气体质量流量,随着充入气泡直径减小,自然循环能力呈增加趋势。在泡状流、弹状流、乳状流和环状流等流型中,随着气体质量流量、质量含气率增加,自然循环能力先增大后减小。随着上升管道高度增加,自然循环流量增大。可见,流动参数显著影响堆芯热工水力特性。现有工作有助于优化带有气泡提升泵的自然循环冷却系统设计。     

垂直上升矩形流道内气液两相流流型图的数值模拟

两相流流型在分析换热、流动不稳定性以及临界热流密度方面具有基础性作用.本文基于VOF(Volume of Fluid)多相流模型,对垂直上升矩形流道内气液两相流动进行数值模拟,表观气速0.1～110 m/s,表观液速0.1～3.2 m/s.得到了流道内气液两相流的主要流型:泡状流、弹状流、搅混流和环状流,分析了流道内截面含气率分布与流型的对应关系,以及截面含气率与气液两相流容积含气率的关系;分析了各种流型下的压降分布特性,并绘制了基于气液表观动能通量的不同流量下气液两相流的流型图,直观的表示出各种流型的分布区域及各流型间的流型转换边界,与已发表文献的实验结果对比符合较好.     

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。     

大L/d倾斜并联光管汽-液两相流不稳定性实验研究

在高压高温试验台上对倾斜并联管汽-液两相流不稳定性进行了实验研究,观察到了压力降型和密度波型等两类不稳定性脉动。在试验管长与管内径比L/d>1200条件下,没有上游可压缩容积时也发生压力降型脉动。系统压力、质量流速、热负荷和进口过冷度等参数对不稳定性有显著的影响。实验表明,在倾斜并联管中,压力降型脉动出现在含气率较低的水动力曲线负斜率段,为两管整体脉动;而密度波型脉动出现在含气率较高的正斜率区域,呈管间脉动。经过对比发现,倾斜并联光管的脉动特性与垂直并联管类似。     

中压沸腾工况相径向分布实验研究

采用高温高压单探头光学探针．在中压沸腾工况下进行了局部空泡率与汽泡频率径向分布特性实验研究,并根据探针信号对两相流流型进行了识别,分析了中压沸腾工况下空泡率径向分布与流型的关系。研究结果表明：随热平衡含汽率增加,整个直径方向上空泡率分布从近U形向鞍形和弧形发展;汽泡频率则以近U形分布为主;泡状流工况下,空泡率呈U形或近壁区显著高于中心区的鞍形分布,弹状流工况下,中心区空泡率略低于近壁区。整个直径上空泡率呈弧形分布。     

含内热源有序饱和多孔介质通道内蒸汽-水两相流型可视化实验研究

采用均一球体形成多孔介质通道,通过高速摄像系统获得了多孔介质通道内两相流动影像数据,识别出多孔介质通道内蒸汽-水两相流动流型存在形式,并研究了部分参数对流型转变的影响规律。结果表明,多孔介质通道内的汽-液两相流型有泡状流、泡状-弹状混合流、弹状流、弹状-环状混合流以及环状流5种;随着入口过冷度的增加,泡状流向过渡流转变以及过渡流向环状流转变时所对应的汽相表观速度呈现出逐渐增大的趋势;随着压力的升高,泡状流向过渡流转变以及过渡流向环状流转变时所对应的汽相表观速度呈现出逐渐减小的趋势。      

气液两相流工况下核主泵的正转全特性研究

在冷却液流失事故(LOCA)事故发生期间,核主泵将处于两相混合运行状态。主要对核主泵的正转全工况不同含气率冷却介质的泵水力性能、流道内部气体体积分布情况及流体流态进行研究,并采用计算流体力学(CFD)模拟计算与气液两相流试验进行验证。研究发现:在正转逆流制动工况,核主泵的扬程曲线随含气率增加整体向下偏移,但其变化规律基本相同。在正转水泵工况和正转正流制动工况,随着流量增加,含气率对核主泵扬程特性的影响逐渐减小,且同流量下核主泵的扭矩和冷却剂介质密度成较为明显的正比关系。     

Pressure wave propagation in air-water bubbly and slug flow

Related to nuclear reactor safety problems, such as the loss of coolant accident caused by some small crevasses in nuclear reactor, choked flows after postulated breaks of hot and cold legs of pressurized water reactors and the boiling flow instability in parallel channels, the characteristics of pressure wave propagation were investigated experimentally for the air-water bubbly and slug two-phase flow in a vertical pipe. Pressure wave was generated from the small pressure disturbance by the up-and-down movement of piston in the test section. Air void fraction was up to 0.7 and superficial liquid velocity was up to 1.5 m/s as experimental conditions. The experimental results show that the pressure wave propagation velocity in bubbly flow decreases acutely with the increase of air void fraction from 0 to 0.05. In slug flow, it is constant when the air void fraction is less than 0.5 but increases gradually when the void fraction increases beyond 0.5. The attenuation coefficient of pressure wave increases with the increase of air void fraction in bubbly flow. The dependency of pressure wave propagation velocity on angle frequency ω in air-water flow shows the dispersion characteristic. The propagation velocity and attenuation coefficient increases gradually with the increase of angle frequency. However, the increase vanishes slowly as the angle frequency reaches 250 Hz in bubbly flow. The propagation of pressure wave in bubbly flow is independent of the superficial velocity of fluids in the range of experiment.     

The measurement of void waves in bubbly two-phase flows

The propagation of void fraction disturbances (i.e. void waves) in bubbly two-phase air-oil flow was investigated experimentally.The void wave data often showed two simultaneous void wave propagations; in particular, the classical kinematic void wave and a faster void wave propagation associated with bubble clusters. Significantly, the bubbly-to-slug flow regime transition was found to be associated with amplification of the void waves associated with the propagating bubble clusters.These data should be valuable for the assessment of the closure laws used in two-fluid models and for the development of mechanistic models for the bubbly-slug flow regime transition.     

Measurements of void fraction by an improved multi-channel conductance void meter

An improved multi-channel conductance void meter (CVM) was developed to measure a void fraction. Its measuring principle is based upon the differences in electrical conductance of a two-phase mixture due to the variation of void fraction around a sensor. The sensor is designed to be flush-mounted to the inner wall of the test section to avoid flow disturbances. The signal processor with three channels is specially designed so as to minimize inherent bias error due to the phase difference between channels. It is emphasized that the guard electrodes are electrically shielded in order not to affect the measurement of two-phase mixture conductance, but to ensure that the electrical fields are evenly distributed in the measuring volume. Void fraction is measured for bubbly and slug flow regimes in a vertical air–water flow and statistical signal processing techniques are applied to show that CVM has good dynamic resolution which is required to investigate the structural developments of bubbly flow and the propagation of void waves in a flow channel.     

Critical Heat Flux Prediction Method Based on Two-Phase Turbulence Model

In this paper, we present an analytical methodology to predict forced convective CHF (Critical Heat Flux) for DNB (Departure from Nucleate Boiling) type boiling transition that occurs inside of uniformly heated round tubes. Axial directional two-phase flow analysis was conducted based on one-dimensional two-fluid model and typical constitutive models. At the same time, the radial directional distribution of void fraction at any axial location was calculated based on the bubble diffusion model, which was coupled with two-phase turbulence model for boiling bubbly flow. The calculated void fraction showed the wall peak distribution, and was compared with experimental data, which was derived from subcool boiling experiments. IPNVG (Incipient Point of Net Vapor Generation), which means the starting point of two-phase flow analysis, was also investigated well, since it was revealed that IPNVG had a significant influence on CHF prediction. By using this methodology for calculating radial directional void fraction distribution, we carried out CHF prediction for water on the assumption that DNB would occur when the local void fraction near the heated wall exceeds a critical value. The predicted CHF agreed well with experimental data, and the accuracy was within about 20%.     

Vertically Downward Two-Phase Flow, (II)

Following Part (I) of the present paper, which presented the experimental results obtained on the void distribution and average void fraction shown by nearly fully-developed, vertically downward two-phase flow of air-water mixture, this Part (?) covers the flow regime transition criteria among the three basic flow regimes : bubbly, slug and annular flows. The annular flow further was divided into two subregions of falling film flow and annular drop flow. The general situation of the transition criteria is as follows : (1) bubbly-to-slug flow transition occurs when the local void fraction in the central region of the tube is 0.3; (2) slug-to-annular drop flow transition criterion is given as a case which equations giving average void fraction for the slug flow and the annular flow are simultaneously satisfied; (3) slug-to-falling film flow transition occurs when the pressure difference between the crest of large wave and the bottom overcomes the surface tension; (4) the occurrence of liquid droplets from wave crests gives the transition criterion between the falling film flow and the annular drop flow.

These criteria were correlated to predict each flow regime boundary respectively considering flow mechanisms or from experimental results. The correlations obtained were compared with published flow regime maps for atmospheric air-water flow and showed satisfactory agreement.     

基于竖直圆管空气-水两相流实验的相间曳力模型研究

研究两相流相间阻力特性对系统程序关键本构模型封闭具有重要意义。本文基于竖直圆管开展了空气-水两相流实验,采用四探头电导探针对空泡份额、气泡弦长和界面面积浓度等气泡参数的径向分布进行了测量。结果表明空泡份额和气泡弦长呈现“核峰型”分布,而界面面积浓度并没有表现出随流速的单调关系。进一步开发了泡状流和弹状流的相间曳力模型,考虑了液相表观流速与管径对气泡尺寸分布的影响,建立了临界韦伯数与不同液相流速的关系。计算得到的空泡份额和界面面积浓度与实验数据整体符合较好,验证了模型的可靠性,为两相流相间阻力特性研究提供参考意义。