基于CFD方法的矩形窄缝通道内过冷流动沸腾模型研究

板状燃料元件中的矩形窄缝通道具有宽高比大的几何特征,高度方向速度梯度大、分布陡峭,发生过冷沸腾时,近壁面汽泡运动行为将受其影响而改变,其中汽泡滑移现象对沸腾换热影响较大。本文针对矩形窄缝通道中的汽泡滑移行为,构建了包含滑移热流的壁面热流分配模型,并建立机理性的汽泡受力模型和滑移模型计算汽泡脱离直径、浮升直径和滑移距离等辅助参数,开发了一套适用于矩形窄缝通道内向上流动沸腾的壁面沸腾模型。选用Nuthel窄缝通道沸腾实验进行数值模拟验证,结果表明：本文模型可以较好地预测1～4 MPa中低压工况窄缝通道向上流动沸腾的壁面过热度,最大误差相比RPI模型由80%降低至17%;蒸发热流份额和近壁面空泡份额相比RPI模型更低。     

基于CFD方法的矩形窄缝通道内过冷流动沸腾模型研究

板状燃料元件中的矩形窄缝通道具有宽高比大的几何特征,高度方向速度梯度大、分布陡峭,发生过冷沸腾时,近壁面汽泡运动行为将受其影响而改变,其中汽泡滑移现象对沸腾换热影响较大。本文针对矩形窄缝通道中的汽泡滑移行为,构建了包含滑移热流的壁面热流分配模型,并建立机理性的汽泡受力模型和滑移模型计算汽泡脱离直径、浮升直径和滑移距离等辅助参数,开发了一套适用于矩形窄缝通道内向上流动沸腾的壁面沸腾模型。选用Nuthel窄缝通道沸腾实验进行数值模拟验证,结果表明：本文模型可以较好地预测1～4 MPa中低压工况窄缝通道向上流动沸腾的壁面过热度,最大误差相比RPI模型由80%降低至17%;蒸发热流份额和近壁面空泡份额相比RPI模型更低。     

竖直矩形窄缝通道内过冷沸腾传热特性的实验研究

以去离子水为工质,在进口压力为0.1～0.3 MPa、质量流速为200～1400 kg·m^-2·s^-1、热流密度为20～320k W·m^-2的参数范围内,对截面参数为50mm×2mm的竖直矩形窄缝通道展开了传热实验研究。实验获得通道内部工质由单相状态到过冷沸腾状态的传热过程曲线,将过冷沸腾段实验值与8个经验公式提供的预测值进行了对比与分析,采用相似原理以及回归分析法,建立了适用于竖直矩形窄缝通道的过冷沸腾准则关系式。研究结果表明,在竖直矩形窄缝通道内,热流密度对过冷沸腾传热具有主导作用;对于本实验的窄缝通道,Bertsch传热公式对于过冷沸腾段的预测效果相较于其他公式更好,本研究所建立的准则关系式与实验数据符合良好。因此,本研究建立的公式能够用于竖直矩形窄缝通道过冷沸腾传热系数的预测。     

矩形窄缝通道内汽泡脱离直径可视化研究

以去离子水为介质,研究热流密度、入口过冷度和质量流速等热工参数对矩形通道内汽泡脱离直径的影响。主要参数如下:主流流体流动方向分别为竖直向上和纵倾45o,压力为0.16 MPa,质量流速G=300~700 kg/(m2.s),热流密度q=27.6~228.3 kW/m2,入口过冷度ΔTsub=20~40℃。研究发现,热流密度和入口过冷度对汽泡脱离直径的影响不明显;随着质量流速的增大,汽泡脱离直径明显减小。     

竖直矩形窄缝通道内近壁汽泡生长和脱离研究

可视化研究窄缝通道内汽泡生长和脱离对于揭示窄缝通道内的沸腾传热机理具有重要意义。本文采用高速摄影仪从宽面和窄面可视化观察了常压条件下矩形窄缝通道内汽泡核化生长和脱离规律。研究结果表明，汽泡在核化点生长时，汽泡底部与加热面存在一小的接触面，总体而言，汽泡在生长过程中基本呈球状。在相同热工参数下，不同核化点处汽泡生长规律基本相同，但汽泡脱离直径相差较大。窄缝通道内汽泡生长速率小，脱离时间较长，可采用修正的Zuber公式预测窄缝通道内汽泡生长直径。在同一拍摄窗口内，统计分析了热工参数对汽泡平均脱离直径的影响规律。随热流密度的增加，汽泡平均脱离直径减小；随入口欠热度的增加，汽泡平均脱离直径减小；随主流速度的增加，汽泡平均脱离直径减小。     

起伏运动对矩形窄缝通道内汽泡直径分布的影响

为进一步探明起伏条件下过冷沸腾两相流相分布特性,采用高速摄像技术和数字成像分析技术,对静止和起伏条件下窄缝通道内汽泡进行可视化实验研究.实验结果表明:随着起伏频率增加,各相位间流道内汽泡直径变化增大.在相同的起伏条件下,增加质量流速将减小各相位间汽泡直径波动幅度.文中给出汽泡平均直径随起伏运动波动幅值的预测关系式,预测结果平均相对偏差为±19.1％.     

强制对流过冷沸腾流体中汽泡脱离频率

在垂直上升环形通道内进行强制对流过冷沸腾实验。实验工质为水，实验压力为大气压力。由一台高速摄像仪对汽泡核化的动力学过程进行图像捕捉。通过影像获取总共58个工况下的汽泡脱离频率。对本实验的数据和从文献中获取的数据进行无量纲分析。将已有的模型和关系式与汽泡等待时间、生长时间以及脱离频率等实验数据进行比较。由池式沸腾改进的关系式未能很好地应用于强制对流过冷沸腾，同时，由过冷沸腾提出的模型也不能预测宽实验参数范围内的汽泡脱离频率。无量纲汽泡脱离频率与无量纲泡核沸腾热流密度相关。新的关系式与现有的低壁面过热度下的实验数据吻合良好。     

竖直窄矩形通道内过冷沸腾传热模型

通过引入池式沸腾-流动沸腾汽泡脱离直径比对沸腾抑制因子S进行了修正,并将修正后的S引入Lee-Mudawwar过冷沸腾CHF模型,通过结合竖直窄矩形通道内的汽泡行为进行分析,建立了适应于竖直窄矩形通道的过冷流动沸腾传热模型,探讨了影响过冷沸腾传热系数的主要因素,并通过将模型预测值与实验值进行对比,验证了模型的可靠,表明当前模型可用于计算竖直窄矩形通道内的过冷沸腾传热特性。     

一种特殊的非对称加热矩形通道临界热流密度实验研究

介绍在高温、高压热工实验装置上进行的垂直上升流条件下一种特殊的非对称加热—单侧加热窄缝矩形通道临界热流密度(CHF)实验研究。实验研究了质量流速、临界含汽量等参数对单侧加热矩形通道CHF的影响规律。研究结果表明,在实验参数范围内,单侧加热与双侧加热的CHF值相差不大,且两者的变化规律基本一致:即在其他热工参数保持不变的情况下,单侧加热CHF随临界含汽量的增加而减小,随入口过冷度的增加而增大;在较低含汽量范围内,单侧加热CHF随质量流速的增加而增大;在较高含汽量范围内则趋势相反。本文提出的单侧加热矩形通道CHF计算关系式在参数范围内计算精度良好。     

大宽高比矩形窄缝通道沸腾起始点实验研究

矩形窄缝通道中的泡核沸腾起始点（ONB）预测对反应堆安全设计十分重要。针对通道尺寸为50 mm×3 mm×1000 mm的竖直矩形窄通道,以去离子水为介质,通过监测壁面温度变化确认ONB的位置,研究了热流密度、质量流速、压力、入口过冷度等参数对ONB发生位置和壁面过热度的影响。收集并评价了已有的8个ONB预测模型,结合实验数据分析得到结论：基于池沸腾的ONB预测模型及其改进模型不能很好的适用于矩形窄通道内,尤其是针对质量流速带来的影响。一些针对矩形通道ONB预测开发的模型可以一定程度上反映ONB点壁面过热度随不同参数变化的发展趋势,但由于实验参数范围不够宽,适用范围和预测精度仍受到限制。结合影响矩形窄缝通道ONB发生的主要因素,推导了适用于计算宽谱参数工况下矩形窄通道中ONB点壁面过热度的解析解形式,并利用实验数据进行了拟合,新关系式超过95%的预测结果与实验结果偏差小于±20%。同时新关系式对其他相关公开文献的ONB数据预测仍在较好的误差范围内。     

低压下水欠热流动沸腾的两相CFD数值模拟研究

采用两流体(汽相和液相)基本数学模型,结合汽相和液相之间的界面传热、传质和动量交换封闭模型、汽泡平均直径模型、汽泡脱离直径模型、汽泡成核模型、汽泡脱离频率模型、欠热沸腾起始点模型和壁面热流密度分配模型,在CFD软件CFX4.4中采用用户自定义函数将相变引起的传热、传质和动量交换作为源项分别添加到汽相和液相的能量、质量和动量守恒方程中,对低压下内管加热外管绝热的环形通道内的欠热沸腾进行了数值研究,得到了欠热流动沸腾下汽相体积份额、液相速度、汽相速度分布等。采用Lee等的环形通道内低压下欠热沸腾体积份额实验数据对计算结果进行了验证,吻合良好。     

基于气泡动力学的过冷流动沸腾边界层模型研究

过冷流动沸腾中的流动和传热特性对反应堆的安全运行和经济性都具有重要意义。过冷流动沸腾起始于ONB点,结束于Tsat点,中间被OSV点划分为高过冷流动沸腾段和低过冷流动沸腾段,不同阶段流场情况以及气泡行为存在较大区别。目前关于过冷流动沸腾过程的研究主要基于宏观实验、理论研究和数值模拟,随着气泡动力学的发展,从微观层面揭示沸腾机理变得可行。本文基于气泡动力学和气泡边界层模型,提出了一套预测过冷流动沸腾的理论模型,采用分相模型,将流场在径向上划分为多个区域,通过1组准二维控制方程,将各区域内的气泡行为,区域间的质量、动量和能量交换以及两相参数沿轴向的变化情况考虑在内,利用获得的边界层流场信息,可确定ONB点和OSV点。模型与空泡份额和流体温度的实验结果符合良好,并成功应用于核反应堆燃料元件通道的过冷流动沸腾计算。     

Predictive study of the incipient point of net vapor generation in low-flow subcooled boiling

A predictive model of the initial point of net vapor generation, incipient point of net vapor generation (IPNVG) for low-flow subcooled boiling is developed in this paper. The IPNVG established in this model meets both the thermodynamic and hydrodynamic conditions. The thermodynamic condition is described by the heat balance at IPNVG. The amount of heat for steam generation is equal to that for bubble condensation at IPNVG. The force balance of the detached bubbles at IPNVG or the hydrodynamic condition is established to provide the diameter of the detached bubbles and the interfacial heat transfer coefficient for the calculation of heat transfer at IPNVG. This mechanism of the present model makes it applicable to low-flow subcooled boiling. Several coefficients involved in the proposed model are identified by Freon-12 experimental data. This model is compared with the experimental data obtained from different works. The data cover two working media of steam-water and Freon-12, two flow conditions of natural and forced circulations and relatively wide ranges of pressure, mass flux and heat flux. The predictions of this model agree with the data quite well.     

过冷流动沸腾中汽泡脱离直径的理论研究

汽泡脱离直径模型是壁面沸腾计算中的一个重要子模型。为了正确预测过冷流动沸腾中的壁面传热情况,研究结合新改进的汽泡生长模型,采用力平衡方法对过冷流动沸腾中的汽泡脱离直径进行了模拟。汽泡生长模型同时考虑了微液层、过热层和汽泡顶部过冷液体层对汽泡生长所做的贡献,并采用饱和沸腾与过冷沸腾2个实验对其进行了验证,结果表明预测曲线与实验值吻合良好。另外,选取了3个过冷流动沸腾实验来验证汽泡脱离直径模型,模拟结果均在可接受的误差范围内。     

Bubble Lift-off Diameter and Nucleation Frequency in Vertical Subcooled Boiling Flow

A series of experiments were carried out to investigate phenomena from bubble nucleation to lift-off for a subcooled boiling flow in a vertical annulus channel. A high-speed digital video camera was used to capture the bubble dynamics. The bubble lift-off diameter and bubble nucleation frequency were evaluated in terms of heat flux, mass flux, and degree of subcooling. The fundamental features of the lift-off diameter and nucleation frequency (i.e., the variations across nucleation sites and the dependence on the flow and heat flux conditions) were addressed based on the present observation. A database for the bubble lift-off diameter was built by gathering and summarizing the data of Prodanovic et al., Situ et al., and the present experiments. We evaluated the predictive capabilities of Unal's model, Situ et al.'s model, and Prodanovic et al.'s correlation against the database. We obtained the best prediction results by modifying the wall superheat correlation in Unal's model. In addition, we suggested a new correlation for a combined parameter of the bubble nucleation frequency and bubble lift-off diameter.     

A mechanistic model of critical heat flux under subcooled flow boiling conditions for application to one- and three-dimensional computer codes

Based on a review of visual observations at or near critical heat flux (CHF) under subcooled flow boiling conditions and consideration of CHF triggering mechanisms, presented in a companion paper [Le Corre, J.M., Yao, S.C., Amon, C.H., 2010. Two-phase flow regimes and mechanisms of critical heat flux under subcooled flow boiling conditions. Nucl. Eng. Des.], a model using a two-dimensional transient thermal analysis of the heater undergoing nucleation was developed to mechanistically predict CHF in the case of a bubbly flow regime. The model simulates the spatial and temporal heater temperature variations during nucleation at the wall, accounting for the stochastic nature of the boiling phenomena. It is postulated that a high local wall superheat occurring underneath a nucleating bubble at the time of bubble departure can prevent wall rewetting at CHF (Leidenfrost effect). The model has also the potential to evaluate the post-DNB heater temperature up to the point of heater melting.Validation of the proposed model was performed using detailed measured wall boiling parameters near CHF, thereby bypassing most needed constitutive relations. It was found that under limiting nucleation conditions; a peak wall temperature at the time of bubble departure can be reached at CHF preventing wall cooling by quenching. The simulations show that the resulting dry patch can survive the surrounding quenching events, preventing further nucleation and leading to a fast heater temperature increase. The model was applied at CHF conditions in simple geometry coupled with one-dimensional and three-dimensional (CFD) codes. It was found that, within the range where CHF occurs under bubbly flow conditions (as defined in Le Corre et al., 2010), the local wall superheat underneath nucleating bubbles is predicted to reach the Leidenfrost temperature. However, a better knowledge of statistical variations in wall boiling parameters would be necessary to correctly capture the CHF trends with mass flux (or Weber number).     

竖直圆管内低压过冷沸腾相分布特性实验研究

实验采用双探头光学探针对内径24 mm竖直圆管内低压过冷沸腾局部空泡份额、界面面积浓度及汽泡尺寸等局部相界面参数径向分布特性进行了研究。实验结果表明：竖直圆管内过冷沸腾相分布形态呈现轴对称特性,随着热流密度的增大,相分布形态出现近壁峰值并逐渐向中间峰值分布形态的发展,较高热流密度工况下出现轴心峰值分布;随着质量流速的增加,局部空泡份额减小,并出现中间峰值向近壁峰值分布形态的转变;随着压力的增大,局部相界面参数减小。     

A mechanistic critical heat flux model for wide range of subcooled and low quality flow boiling

A mechanistic model to predict a critical heat flux (CHF) over a wide operating range in the subcooled and low quality flow boiling has been proposed based on a concept of the bubble coalescence in the wall bubbly layer. The conservation equations of mass, energy and momentum, together with appropriate constitutive relations, are solved analytically to derive the CHF formula. The model is characterized by an introduction of the drag force due to wall-attached bubbles roughness in the momentum balance, which determines the limiting transverse interchange of mass flux crossing the interface of the wall bubbly layer and core. Comparison between the predictions by the proposed model and the experimental CHF data shows good agreement over a wide range of parameters for both light water and fusion reactors operating conditions. The model correctly accounts for the effects of flow variables such as pressure, mass flux and inlet subcooling as well as geometry parameters.     

复合换热管过冷沸腾换热实验与关联式评价

以去离子水为实验介质,在单面受热流密度条件下,开展了聚变装置偏滤器的过冷流动沸腾强化换热特性实验研究,将内肋强化换热技术与内插扭带结构相结合,利用两者的协同强化传热效应,设计出一种复合换热管。实验参数为：质量流速,992～4 960 kg/(m2·s);压力,04～2 MPa;入口过冷度,8701～11921 ℃;热流密度,1～163 MW/m2。对4种强化换热管（光管、内插扭带管、内螺纹肋管和复合换热管）的管内过冷流动沸腾换热特性和综合性能评价指标（PEC）进行了对比实验。结果表明：与其他3种管道相比,复合换热管的对流换热系数和PEC最高,传热特性最好。研究了复合换热管的扭带扰动比、螺距、压力和质量流速对管内两相流动对流换热系数的影响规律,发现对流换热系数与螺距、质量流速呈正比,与扭带扰动比、压力呈反比。最后对比了4个现有的过冷流动沸腾换热经验公式,并在无量纲模型基础上,增加了扰动比和螺径比（t/Dh）进行修正,利用非线性拟合方法提出了适合复合换热管过冷流动沸腾的努塞尔数新公式。