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1.
在地震等行为产生的非线性振动下,两相流体会影响回路传热并对装置结构进行冲击,因此对气液界面行为的把握对核安全具有十分重要的意义。本文通过将振动装置与两相流实验回路相结合的方法,对非线性振动下水平通道内气液两相流问题进行了实验研究。基于FLUENT平台,结合动网格模型及UDF编程手段建立了数学模型,并对数学模型进行验证。研究结果表明:模拟结果与实验结果具有很好的一致性;振动工况下气液两相流动形式不同于稳态工况,会出现更复杂的气液界面,主要流型有泡状流、弹状流、搅拌流、波状流及环状流;瞬时摩擦压降的波动幅度随振动幅度和频率的增大而增大,且与振动幅度相比,振动频率对其影响更大。  相似文献   

2.
《核动力工程》2017,(2):38-42
为研究实验段振动对管内两相流局部参数变化的影响,利用电导探针技术对振动状态下局部两相流特性参数包括空泡份额、气泡直径和界面浓度进行了测量。实验首先在静态工况下进行,通过固定在实验段上方的偏心轮转动获得振动工况。实验段振动周期保持在0.5 s,偏心轮提供的振动幅度分别为4.8 mm、9.5mm和15.8 mm。实验结果表明,振动对环管内气-水两相流局部时均参数分布影响很小。但振动引起的附加惯性力作用使两相流局部参数径向分布在实验段振动周期中发生明显变化,而且局部参数的变化幅度随实验段振幅的增加而显著增大。在含气率较低的流动工况,当振幅增大到15.9 mm时振动工况下径向空泡份额峰值较静态工况下的空泡份额峰值的增量可以达到70%。但振动对局部流动参数的影响随气流量增大而降低。  相似文献   

3.
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。  相似文献   

4.
振动工况下环管内气液两相流参数分布实验研究   总被引:1,自引:1,他引:0  
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。  相似文献   

5.
本文对不同起伏非线性振动条件下倾斜上升管内气液两相流流型及转变规律进行实验研究,借助高速摄影仪对起伏非线性振动状态下气液两相流的流型进行分类。结果表明,倾斜上升管气液两相流有弥散泡状流、起伏弹状流、准弹状流和液环式环状流4种。对弥散泡状流向起伏弹状流和准弹状流向液环式环状流的转变机理进行分析,在稳定状态转变机理的基础上引入振动参数,建立了考虑振动加速度的关系式。本文建立的流型转变关系式与实验结果吻合较好。  相似文献   

6.
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。  相似文献   

7.
通过孔口的收缩-膨胀增强气液接触是强化气液两相传热传质的重要方式,其中孔口边缘的液膜厚度则是建立气液两相传递过程动力学模型的关键参数。基于孔口流动时的气液相力平衡原理,建立了气液两相并流向下通过孔口的液膜厚度模型,并将模型预测的液膜厚度与管道环状流液膜厚度进行了对比分析,表明了新模型的有效性和广泛适用性。基于新建液膜模型,从流体受力的角度分析了气液流量、液相运动黏度以及孔口直径等参数对液膜厚度的影响。结果表明:随气相流量提高,气液界面速度增大,气液界面剪切力增强,无因次液膜厚度随之减薄;液相流量增大,气相流通面积减小,气相流速增大,尽管气液界面剪切力及气液界面速度均有所增大,但液量的直接增量最终导致无因次液膜厚度增厚;液相运动黏度增加,尽管气液界面剪切作用增强,但气液界面速度减小,液膜厚度增厚;相同流量下,孔口直径增大,气液界面剪切力及气液界面速度均减小,液膜厚度随之增加。  相似文献   

8.
首先采用系统性人因失误减少和预测方法(SHERPA)分析操纵员界面管理任务中的关键行为;再用行为分析软件(INTERACT9)分析国内某数字化核电厂全范围模拟机上操纵员的操作录像视频,之后对INTERACT9采集的关键行为数据进行统计分析,得到4个操纵员界面管理任务的一般特征:①一、二回路操作员操作菜单栏、选择监视目标和打开参数界面的频率最高;②操纵员在选择进入不同系统界面的方式上趋向于选择从菜单栏进入;③一回路操纵员在正常工况和事故工况下的界面管理任务没有明显差异;二回路操纵员在正常工况下的界面管理任务明显少于事故工况;④正常工况下,一回路操纵员的界面管理任务显著多于二回路操纵员;事故工况下,一回路操纵员的界面管理任务与二回路操纵员的的界面管理任务相当。   相似文献   

9.
《核动力工程》2015,(5):187-193
窄小流道内的两相流动压降不同于常规流道,在窄小空间内的受限气泡行为对流动稳定性有着重要影响。本文在1个标准大气压(0.101 MPa)下,对内径为2 mm的窄小流道内气-液两相流动进行可视化实验研究。实验在不同工况参数和气相工质下展开,其中气相工质包括氮气、空气、二氧化碳和氩气,液相工质为水。研究发现,在给定气相体积流量下,压降随液体质量流速增大而增加,对应的气-液界面形态均为拉长型气弹;而在给定液相质量流速下,压降随气相体积流量增加不成线性关系,是先减小后增大,对应的气-液界面形态仍为拉长型气弹。  相似文献   

10.
水平管气-液两相分层流底部小破口泄漏预测   总被引:1,自引:0,他引:1  
对分层流型下破口位于水平管底部的气-液两相泄漏量进行了实验测量和理论预测研究.设计了新型破口泄漏测量装置,测试管道直径为40mm,采用布置在管壁上的直径为2.5mm的圆孔模拟破口,避免了传统泄漏测量装置用短管代替破口从而导致实验模拟与实际泄漏工况出现较大偏差的缺点.提取了气-液界面高度和破口两侧差压作为特征参数,构建了径向基函数神经网络,对破口质量含气率进行了预测,破口质量流量由修正的两相流孔板公式计算.实验结果表明,质量含气率及流量预测值与实验吻合良好.  相似文献   

11.
The flow pattern and transition law of gas-liquid two-phase flow in inclined rising pipe under different fluctuant nonlinear vibration conditions were studied experimentally. The flow patterns of gas-liquid two-phase flow under fluctuant nonlinear vibration condition were identified by using high-speed camera. The results show that there are four kinds of patterns in inclined rising pipe with diffuse bubble flow, fluctuant slug flow, proto slug flow and liquid-ring annular flow. The mechanisms of the transition from diffuse bubble flow to fluctuant slug flow, proto slug flow to liquid-ring annular flow were derived, the vibration parameter was added on the basis of the steady state transition mechanism and the flow pattern transition formulae considering the vibration acceleration were established. The results show that the flow pattern transition formulae established in this paper agree well with the experimental results.  相似文献   

12.
The effect of nonuniform magnetic field on the linear and nonlinear wave propagation phenomena in two-phase pipe flow of magnetic fluid is investigated theoretically to realize the effective energy conversion system using boiling two-phase flow of magnetic fluid. Firstly, the governing equations of two-phase flow based on the unsteady thermal nonequilibrium two-fluid model are presented and the linear void wave propagation phenomena in boiling two-phase flow are numerically analyzed by using the finite volume method. Next, the nonlinear pressure wave propagation in gas-liquid two-phase flow is numerically analyzed by using the finite different method. According to these theoretical studies on the wave propagation phenomena in two-phase flow of magnetic fluid, it seems to be a reasonable proposal that the precise control of the wave propagation in two-phase flow is possible by effective use of the magnetic force.  相似文献   

13.
Effect of flow-induced vibration on local flow parameters of two-phase flow   总被引:1,自引:0,他引:1  
A preliminary study was conducted experimentally in order to investigate the effect of flow-induced vibration on flow structure in two-phase flow. Two kinds of experiments were performed, namely ‘reference’ (no vibration) and ‘vibration’ experiments. In the reference experiment, an experimental loop was fixed tightly by three structural supports, whereas the supports were loosen a little in the vibration experiment. In the vibration experiment vibration was induced by flowing two-phase mixture in the loop. For relatively low superficial liquid velocity, flow-induced vibration promoted the bubble coalescence but liquid turbulence energy enhanced by the vibration might not be enough to break up the bubble. This leaded to the marked increase of Sauter mean diameter, and the marked decrease of interfacial area concentration. Accordingly, flow-induced vibration changed the void fraction profile from ‘wall peak’ to ‘core peak’ or ‘transition’, which increased distribution parameter in the drift-flux model. For high superficial liquid velocity, shear-induced liquid turbulence generated by two-phase flow itself might be dominant for liquid turbulence enhanced by flow-induced vibration. Therefore, the effect of flow-induced vibration on local flow parameters was not marked as compared with that for low superficial liquid velocity. Since it is anticipated that flow structure change due to flow-induced vibration would affect the interfacial area concentration, namely interfacial transfer term, further study may be needed under the condition of controlled flow-induced vibration.  相似文献   

14.
汽液两相流动不稳定性的小波包研究法   总被引:2,自引:0,他引:2  
利用小波包对信号的精确细分特性,对汽液两相流动密度波不稳定性的脉动信号进行分析,并由此得到两相密度波不稳定性脉动的特征向量。由这些特征向量可得到汽液两相流动脉动能量随脉动频率的分布状况,开创了对汽液两相流动密度波不稳定性研究的新视角。  相似文献   

15.
Two-phase flow instability of natural circulation under a rolling motion condition is experimentally studied. The experimental results show the rolling motion induces a fluid flow fluctuation. At the trough point of the flow fluctuation, rolling motion can cause the early occurrence of natural circulation two-phase flow instability, and this case is defined as trough-type flow oscillation. The system stability decreases with increasing rolling amplitude and effect of rolling frequency is nonlinear. The complex overlap effect of trough-type flow oscillation and density wave oscillation can enhance the system coolant fluctuation; this case is defined as complex flow oscillation. Complex flow oscillation may be divided into two types: regular and irregular complex flow oscillations. Irregular complex flow oscillation is a transition type from trough-type flow oscillation to regular complex flow oscillation. Under the same thermal hydraulic conditions, the marginal stability boundary (MSB) of regular complex flow oscillation is similar to that of density wave oscillation without rolling motion, and the influences of rolling parameters on the MSB are slight.  相似文献   

16.
《Annals of Nuclear Energy》2005,32(3):299-329
On the basis of the homogeneous flow model and Galerkin nodal approximation method, this study adopts the methodology in [Nucl. Eng. Des. 192 (1999) 31] to develop a nonlinear numerical model for a double-channel two-phase natural circulation loop. The calculated steady-state results provide a reasonable agreement against the experimental data in the high power region but overestimate in the low power region under both equal-heating and unequal-heating conditions. Nonlinear dynamics and stability boundary of the double-channel boiling natural circulation loop are also analyzed. Two unstable regions, type-I and type-II instabilities, are found in this system. Complex channel-to-channel interactions coupling with loop dynamics may occur in the double-channel natural circulation loop. For the equal-heating system, out-of-phase oscillations may prevail under the operating conditions that the gravitational pressure drops are very highly dominant, such as low subcooling and low power conditions. However, in-phase oscillations may exist in the medium to high power regions, where two-phase frictions are relatively important. For the unequal-heating system, the heating power difference between two channels may drive the system more unstable both in type-I and type-II regions. The two unequal-heating channels exhibit in-phase oscillation mode, instead of out-of-phase in the equal-heating system, at low subcooling and low power conditions. In addition, parametric effects on the stability are also evaluated in this study.  相似文献   

17.
An experiment was performed on the natural circulation test loop HRTL-5, which simulates the geometry and system design of the 5 MW full power natural circulation nuclear heating reactor. Different flow modes, including density wave oscillation and flow excursion et al., were observed in a wide range of inlet sub-cooling at 1.5MPa. By means of self-developed computational codes, the bifurcation chart has been obtained. Consequently the flow excursion boundary has been determined. Through the analysis on the excursion boundary, the method to avoid the flow excursion during startup has been presented. Analytical results show: (1) with the decreasing heat flux or the increasing system pressure, the static flow excursion occurs at higher inlet temperature and its range in the instability maps becomes narrower correspondingly; (2) to decrease the outlet two-phase resistance or increase the inlet single-phase resistance is beneficial to avoid the flow excursion; (3) by means of increasing the system pressure to start up the reactor with low heat flux, the flow excursion and low steam quality density wave oscillation can be successfully avoided. This investigation is meaningful to the reactor safety and the design of the nuclear heating reactors.  相似文献   

18.
为深入分析沸腾两相流动振荡诱发沸腾临界的影响特性,本文以去离子水为工质,横截面19 mm×19 mm、中心为外径9.5 mm的单棒通道为研究对象,通过在不同热工参数下开展沸腾两相流动特性可视化实验研究,结合汽泡行为和汽-液界面特性,分析流动振荡诱发沸腾临界的影响特性。研究结果表明,低压力、低质量流速和低入口过冷度下,极易出现流动振荡,并导致沸腾临界提前发生,此时的临界热流密度与稳定工况下相比明显偏低;随着壁面热流密度不断增加,流道中两相流型先后出现泡状流、弹状流、合并弹状流、搅混流、剧烈搅混流、不稳定环状流;当流动出现剧烈振荡时,流道存在回流;发生沸腾临界时流道压降波动最大,对应的流型为不稳定环状流。因此,单棒通道内流动振荡可能会导致沸腾临界提前发生。   相似文献   

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