内螺纹管临界热流密度预测与数值计算

基于壁面汽泡壅塞理论,针对近临界压力区两相流动沸腾的偏离泡核沸腾(DNB)现象,对垂直上升内螺纹管的DNB型临界热流密度(CHF)进行了数值计算研究。以内螺纹管为分析对象改进已有的汽泡壅塞模型,计算了汽泡层区与主流区的极限传递质量流量、湍流速度分布、汽泡层区临界截面含气率等本构关系,汽泡脱离直径的计算考虑了汽泡接触角的影响。本文模型还根据大量CHF实验数据拟合得到了新的α_b关联式。最后,基于Fortran语言编制了CHF的理论预测数值模型程序,研究分析了压力、质量流速、热平衡干度及进口欠焓对CHF的影响,并根据CHF查表值对本文模型进行评估,同时将实验得到的内螺纹管CHF数据与采用Bowring模型、Katto模型、Shah模型和本文模型计算的CHF进行比较,发现本文模型的误差最小,与实验值吻合结果较好,说明本文模型能较好地对垂直上升内螺纹管DNB型CHF进行预测。     

基于液膜蒸干模型的低压低流量环状流CHF理论研究

为对低压低流量下的环状流临界热流密度（CHF）进行预测,建立了考虑液膜蒸发、液滴沉积和夹带的液膜蒸干模型,并用已有的实验数据对其进行验证。计算结果表明：在实验参数范围内,CHF计算值与实验值相对偏差在25%以内,两者符合较好。以建立的环状流CHF模型为基础,研究了进口焓差、质量流速、管径和加热长度对CHF的影响。该模型能够有效地计算低压低流量环状流CHF和分析CHF随不同参数的变化趋势。     

环形窄缝通道内干涸型临界热流密度的理论研究

在双面加热的垂直环形窄缝通道内,对向上流动环状流的临界热流密度(CHF)进行理论研究,以质量、动量和能量守恒方程为基础建立数学物理模型。对该模型进行数值求解,得到了不同窄缝间隙通道内的CHF和临界含汽率的关系曲线,分析得出压力对CHF的影响,并将理论计算值与实验值进行比较。     

汽液两相临界流动的热力学非平衡两流体模型

提出了热力学非平衡两流体临界流六方程模型，并对汽泡增长方程，流体状态方程和基本结构关系式进行了改进。利用本模型成功地预测了本试验中的实验结果，并利用前人的实验数据验证了其通用性。此外还利用本模型分析了在临界流动中各参数的变化及破口通道长径比、破口通道直径，起始汽泡密度和汽泡直径对两相临界质量流速的影响。     

矩形窄缝通道临界热流密度数值预测

利用已有的实验数据对Weisman模型和Kwon模型的计算结果进行计算与分析.结果表明:2套模型计算偏差分布趋势相似,但Kwon模型的分散度较小,精度更高.对于矩形窄缝通道,已有的汽泡壅塞模型预测精度较差;不宜将汽泡壅塞模型直接用于矩形窄缝通道.结合矩形窄缝通道自身的特性对其中的Kwon模型进行了拓展.改进后的模型具有...     

基于CFD方法的棒束通道内临界热流密度预测

为研究棒束通道内临界热流密度现象,采用基于对气、液两相分别建立基本守恒方程的欧拉两流体六方程模型和改进的壁面热流密度分配模型,利用CFD商用软件FLUENT 14.5对捷克大型水介质实验回路上开展的临界热流密度（CHF）实验进行数值模拟。通过计算获得CHF发生前、后计算域内重要热工水力参数的分布及CHF发生值,将CFD计算获得的CHF与实验测得值进行对比,结果表明,大多数工况的偏差在±30%以内,证明了欧拉两流体模型结合改进的壁面热流密度分配模型对CHF预测的准确性。本研究可为复杂结构的CHF预测提供依据。     

严重事故条件下反应堆压力容器下封头CHF模型应用研究

根据堆芯熔融物滞留(IVR)措施与压力容器的传热特点,对界面脱离临界热流密度(CHF)分析理论模型和考虑单个汽泡汽-液界面动力学的CHF分析理论模型分别进行改进,建立综合的CHF预测模型以应用于压力容器下封头CHF分析。结果表明,本文的综合模型预测的下封头CHF结果与国际上一些大尺寸的弯曲表面实验结果基本一致。     

基于矩形窄缝通道实验数据的DNB机理模型评价

偏离泡核沸腾（DNB）对于压水堆安全具有重要意义。已有机理模型能否适用于矩形窄缝通道缺乏足够的实验验证。本文基于矩形窄缝通道实验数据,对微液层蒸干模型和汽泡壅塞模型两类DNB机理模型进行了计算评价。结果显示：汽泡壅塞模型适用范围较微液层蒸干模型宽;部分热工参数对模型计算性能有系统性影响。随空泡份额的增大,各模型的计算性能均变差,可能是通道几何差异所致。     

矩形小流道受限汽泡流及环状流区域沸腾传热模型研究

为探析矩形小流道受限汽泡流及环状流区域沸腾传热机理,本文基于理论推导,从受限汽泡典型特征出发,探明了受限汽泡流几何结构;基于时间加权平均方法,确定了受限汽泡区及液塞区在受限汽泡流所占权重;基于一维导热等理论和积分方法,建立了液膜蒸发换热系数计算方法,并将其应用于环状流区域。综合上述方法,提出了一种新的受限汽泡流及环状流区域沸腾传热模型——双区域模型,该模型适用范围为:雷诺数（Re）为2300~5373,普朗特数（Pr）为2.75~19.8,毛细数（Ca）为0.000835~0.002767。      

水平圆管临界热流密度实验研究

对水平圆管内低质量流速临界热流密度(CHF)进行了实验研究和分析。实验研究发现,水平流动圆管沸腾临界发生在圆管加热壁面顶部。通过对沸腾临界发生时圆管出口的质量含汽率和流型进行分析发现,本文研究的参数范围内沸腾临界时的出口含汽率高,流型为环状流,沸腾临界类型为干涸型(Dryout)。将经验公式预测值与实验结果进行比较发现,Bowring公式和Lookup table的预测值远大于CHF的实验值。导致此现象出现的主要原因为:Bowring公式和Lookup table是基于竖直流动CHF实验数据开发的模型,水平流动时在重力的作用下环状流液膜呈非均匀分布,顶部液膜干涸提前触发沸腾临界造成CHF值降低。     

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).     

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.     

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%.     

A critical heat flux model based on mass, energy, and momentum balance for upflow boiling at low qualities

A mechanistic modeling of critical heat flux (CHF) in upflow boiling at low qualities is performed. The developed model is based on a physical criterion of CHF occurrence and a mechanism limiting the thermal transport between a stagnant bubbly layer and bulk stream. The mechanism can be mathematically formulated by coupling the equation of limiting mixing mass flux, which is derived from momentum balance equations in two regions, with local mass and energy balance equations on the bubbly layer. The resulting form of the model is represented by a general and straightforward CHF formula involving two empirical constants related to the void fraction and the thickness of the bubbly layer. The predictions agree well with the extensive CHF data of water in uniformly heated tubes.     

倾斜管内上升泡状流界面参数分布特性实验研究

采用双头光纤探针对倾斜圆管内空气-水两相泡状流界面参数分布特性进行了实验研究,包括局部空泡份额、气泡通过频率、界面面积浓度及气泡当量直径径向分布特性。实验段内径为50 mm,液相表观速度为0.144 m/s,气相表观速度为0~0.054 m/s。结果表明倾斜管内向上泡状流气泡明显向上壁面聚集。局部界面浓度、空泡份额及气泡通过频率径向分布相似。倾斜条件下局部界面参数分布下壁面附近峰值相对于竖直状态被削弱甚至消失,上壁面附近峰值被加强,中间区域从下壁面往上逐渐增大,且随倾斜角度的增加变化更加剧烈。气泡等价直径随径向位置、气相速度及倾斜角度的不同无明显变化,气泡聚合和破碎现象较少发生。通过气泡受力分析解释了倾斜对泡状流局部界面参数分布的影响机理。     

圆管内中低含汽率下临界热流密度的数值预测研究

采用汽泡边界层的形成和长大,造成近壁区泡泡雍塞,从而阻碍汽泡层和主流区的湍流交换的机理,建立了圆管中低含汽率临界热流密度的预测理论模型。经过与Ｔｈｏｍｐｓｏｎ和ＭａｃＢｅｔｈ的ＣＨＦＲ数据库比较,表明在圆管内中低含汽率工况下,预测结果和实验数据符合得较好,本文所提出的模型可用于圆管内中低含汽率工况下ＣＨＦ值的预测。     

氧化铝纳米流体增强球形下封头IVR能力边际研究

为评价氧化铝纳米流体相对于纯水工质对球形下封头熔融物滞留（IVR）能力边际的拓展程度,采用基于气泡力平衡的氧化铝纳米流体临界热流密度（CHF）机理模型和壁面热通量拆分CHF模型计算球形下封头外表面纳米流体CHF。利用熔融物堆内滞留分析软件CISER开展衰变热分布抽样计算,得到下封头壁面CHF随倾角变化的随机分布,并将其与纳米流体CHF模型的理论值相比,以CHF比值小于1作为IVR成功准则,研判纳米流体对IVR能力边际拓展的影响程度。研究结果表明,若不对下封头内外传热构成采取任何优化措施,仅采用纳米流体替代纯水工质,压水堆核电厂的IVR能力边际能够拓展至1300 MW额定电功率水平。      

近壁滑移汽泡沸腾换热机理研究进展

在沸腾换热机理研究中,近壁滑移汽泡的研究日益受到广泛的重视.但是,近壁滑移汽泡的研究还远未成熟.本文探讨了近些年来滑移汽泡换热机理方面的最新研究进展.论述了滑移汽泡的动力特性和换热机制;总结了近壁滑移汽泡的换热机理模型及其计算方法.指出了近壁滑移汽泡动力特性所需要继续深入研究的内容,初步构建了近壁滑移汽泡换热机理模型.最后对近壁滑移汽泡的研究方向提出了建议.     

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。