AP1000旋叶式汽-水分离器分离效率与压降的数值模拟

建立基于拉格朗日-欧拉方法的气-液两相流动的数学模型,利用商用计算流体力学软件CFX对该模型求解,数值模拟几何缩比后AP1000旋叶式汽-水分离装置内部冷态工况下气-液两相流动特性。模型中空气为连续相,其内运动的液滴视作离散相,针对液滴在流场中的运动特点,考虑液滴受到曳力、虚拟质量力、浮力和重力,并以此建立空气和液滴动量双向耦合的动力学模型。针对9个不同工况,利用CFX软件对两相流模型进行求解,得到不同直径大小的液滴在流场内的运动轨迹,进而得到分离器的分离效率和进出口总压降。结果显示:分离效率的计算值与冷态实验数据非常吻合,且压降计算值与冷态实验值变化趋势基本一致,验证所建立模型的正确性。     

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。     

波形板汽水分离器内分离效率的影响因素分析

基于壁面液膜模型，进行无钩波形板汽水分离器内液膜生成情况的三维数值模拟，模拟中采用Realizable k-ε模型和壁面液膜模型对波形板内的气相和液相进行数值模拟计算，根据模拟结果分析波形板内的分离效率。研究结果表明：在不改变波形板的结构和不考虑二次携带的前提下，随进口速度或液滴直径的增加，壁面形成液膜面积和高度增加，分离效率也随之提高。当进口速度和液滴直径一定时，液膜高度和面积随蒸汽湿度的增加呈先增加后减小的趋势，当湿度达到10%时，液膜高度和面积达到最大，分离效率最佳。     

曲率对竖直向上环形狭窄通道内环状流特性的影响

基于三流体分离流模型，以液膜质量、动量和能量守恒方程为基础，结合汽芯动量方程，对双面加热垂直向上流动环形狭窄通道内环状流特性进行数值模拟。将计算结果与实验结果相比较，两者符合较好。通过数值模拟，分析了曲率对环状流特性的影响，得到了曲率对液膜厚度、液膜内温度、液膜内速度、临界热流密度等的影响曲线。曲率越大，内液膜越薄，而外液膜越厚。内管干涸时，临界热流密度随曲率的减小而增大；外管干涸时，则反之。     

氢气安全分析软件CYCAS的研发及初步验证

基于计算流体力学方法进行了三维氢气安全分析软件CYCAS的自主研发,采用隐式连续欧拉-任意拉格朗日欧拉方法求解三维、可压、非定常的Navier-Stokes方程组。CYCAS通过求解多组分的质量守恒方程描述多组分气体的扩散和混合,气流中的水蒸气相变行为采用均相平衡模型模拟,而壁面上的相变行为采用Chilton-Colburn相似假设,湍流模拟选用了代数湍流模型和k-ε湍流模型。采用喷射实验HYJET和国际标准测试题ISP23对CYCAS进行了初步验证,计算结果与实验值吻合良好。     

基于欧拉-拉格朗日方法的气载核污染物长距离传输沉降模拟研究

在气载核污染物长距离传输沉降方面，欧拉-拉格朗日方法能够结合拉格朗日方法和欧拉方法两种理论的优势，国内对其研究较少。假设我国某核电厂在发生类似福岛核泄漏事故的情况下，针对核污染物在大气中的长距离输运过程，通过应用JRODOS(Java Real-time On-line Decision Support)系统中MATCH(Multi-scale Atmospheric Transport and Chemistry)模块的欧拉-拉格朗日方法，开展数值模拟研究，并将地面沉降结果及剂量率场分布情况，结合实况天气图进行趋势验证。模拟与验证的结果体现了湿沉降在核污染物清除中的重要作用，同时表明欧拉-拉格朗日方法能够给出核污染物在大气中长距离传输和沉降的主要特征，模拟结果与天气实况在趋势上较为符合，该方法可以为我国核事故后果评价及应急决策提供辅助参考。     

竖直环形狭缝通道内环状流的预测模型

对竖直环形狭缝通道内环状流流动沸腾传热理论模型进行了分析，以液膜质量、动量和能量守恒方程为基础，结合汽芯动量方程建立了竖直环形狭缝通道内环状流的数学物理模型。对该模型进行数值求解，得出了液膜厚度、液膜内的速度分布和温度分布、内—外管的换热系数以及通道内压降值，并与实验值进行了比较。     

气泡破裂产生膜液滴现象可视化实验研究

气泡破裂产生液滴的现象普遍存在于核电厂蒸汽发生器中，由此产生的液滴是蒸汽流夹带液滴的主要来源之一。本工作利用可视化装置及高速摄像技术拍摄气泡在自由液面处破裂产生液滴的实验现象。结果表明，在实验气泡尺寸范围内，气泡液帽破裂产生膜液滴形式都是单点破裂，首先液膜进行排液，其后液帽顶部或底部产生孔隙，然后孔隙迅速扩大、液膜卷曲形成液体环，最终发生不稳定射流形成细小的膜滴。对实验数据进行拟合，得到气泡等效半径在3~25 mm范围内膜液滴数量同气泡尺寸关系式，实验结果与前人结果变化趋势相似。     

临界热流密度后膜态沸腾传热研究

本文简要地叙述了临界热流密度后流动膜态沸腾的现状后,全面地介绍我们在弥散流和逆环状流膜态沸腾方面的实验和理论研究。集中讨论低压小流量下的膜态沸腾研究,实验范围为:弥散流P=2-7bar,G=25—130kg/m~2s,x_λ=5-85％,q=20—95kW/m~2;逆环状流p=3-7bar,G=45—160kg/m~2·s,Δt_(subλ)=1—20℃q=50—90kW/m~2。简要地讨论了弥散流的理论模型及其与实验比较;逆环状流物理模型以及现有经验式与实验比较。弥散流研究虽然比较深入,但尚缺乏液滴信息,因此待定常数尚较多,这是今后研究的重点。逆环状流实验研究,一般仅提供壁温数据,尚未发现关于汽膜特征方面的信息,而且壁温数据也极为稀少,因而目前的经验式极不完善,更无合适的计算模型。只有在突破了汽膜特征研究方面的困难后,才有可能为逆环状流计算模型提供验证基础。尽管目前国际上膜态沸腾研究十分活跃,但是实验数据库仍然十分贫乏,应当进一步有组织地进行一系列实验研究。     

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。     

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.     

Two Phase Pressure Drop Multipliers and ICE Technique Applied in a Multibubble Slug Ejection Model

Two-phase flow of coolant is described in subassemblies of liquid metal fast breeder reactors by a one-dimensional two-phase multibubble slug ejection model. Vapor flow of sodium between the slugs is modeled as annular flow with a moving liquid film of variable thickness wetting structural surfaces. The two-phase pressure drop multiplier concept introduced by Lockhart-Martinelli is used in the frame of the slug ejection model with an algorithm that simultaneously computes interfacial friction coefficient and liquid film axial velocity distribution. The implicit continuous Eulerian (ICE) technique developed by Harlow and Amsden for computing pressure distribution in a continuum medium is applied in heterogeneous two-phase flow to the governing equations for the vapor phase. This solution method is more stable than the numerical solution by finite differences of the vapor momentum equation.     

A simple model for vertical annular and horizontal stratified two-phase flows with liquid entrainment and phase transitions: one-dimensional steady state conditions

A simple one-dimensional three-fluid model is presented for the simulation and analyses of vertical annular and stratified horizontal or inclined two-phase flows. The model has been verified for various experimental data: developing annular flow, momentum transfer in an annular flow, plane flow with a hydraulic jump, flooding in a horizontal pipe, and stratified flow with direct steam condensation. Emphasis has been laid upon several mass, momentum and energy interfacial transfer processes. New correlations are proposed for the droplet entrainment intensity in annular flow and for steam direct contact condensation on the liquid film in a stratified flow. The liquid entrainment in the annular flow is correlated with the liquid film thickness. Direct contact condensation is correlated with the turbulent convective heat transfer in the liquid film. It has been shown that the present model is able to predict all dominant processes in both types of flow.     

Wall friction in annular-dispersed two-phase flow

Modeling of wall-liquid film friction in annular and annular-dispersed two-phase flow regimes, and its effect on the performance of two-fluid models are addressed. It is shown that calculation of the wall friction based on the frictional pressure gradient, found from the widely applied empirical correlations for two-phase frictional pressure drop, can lead to significant underprediction of the liquid film thickness, and can result in the prediction of unphysical hydrodynamic characteristics for the film. In contrast a method which models wall-liquid film friction by applying the shear stress-shearing strain relation based on the film velocity profile is shown to adequately predict the liquid film hydrodynamic characteristics.     

Prediction of the critical heat flux in annular regime in various vertical channels

The axial variation of film flow rate in annular regime was analyzed to predict the critical heat flux in water saturated flow boiling in various vertical channels. In the analyses, several quantities including the deposition and entrainment rates of droplets were evaluated with the correlations that were based on the separate experimental data of film flow rate and droplet flow rate in annular flow; model closure was achieved without introducing arbitrary constants. The predicted results were compared with extensive data of critical heat flux in flow boiling. Fairly good agreements were observed for the critical heat fluxes in round tubes with uniform and axially non-uniform heating and in non-circular shaped channels without sharp corners. It is hence expected that the important processes for the onset of critical heat flux condition in annular regime were satisfactorily described in the model. However, the critical heat fluxes were generally overestimated in thin rectangular channels with sharp corners. The non-uniform distribution of liquid film in channel cross-section would be the primary reason of the disagreement.     

环形狭缝通道内环状流模型的数值分析

对环形狭缝通道内的环状流建立了分离流模型。应用质量、动量和能量守恒方程 ,加上相应的边界条件和使方程组封闭的经验关系式 ,对环形狭缝通道的内、外液膜厚度、液膜内的速度分布和温度分布 ,以及内、外管的换热系数进行了数值计算求解     

Effect of Moderator Density Distribution of Annular Flow on Fuel Assembly Neutronic Characteristics in Boiling Water Reactor Cores

The effect of the moderator density distribution of annular flow on the fuel assembly neutronic characteristics in a boiling water nuclear reactor was investigated using the SRAC95 code system. For the investigation, a model of annular flow for fuel assembly calculation was utilized. The results of the assembly calculation with the model (Method 1) and those of the fuel assembly calculation with the uniform void fraction distribution (Method 2) were compared. It was found that Method 2 underestimates the infinite multiplication factor in the fuel assembly including the gadolinia rod (type 1 assembly). This phenomenon is explained by the fact that the capture rate in the thermal energy region in gadolinia fuel is estimated to be smaller when the liquid film of annular flow at the fuel rod surface is considered. A burnup calculation was performed under the condition of a void fraction of 65% and a volumetric fraction of the liquid film in liquid phase of 1. It is found that Method 2 underestimates the infinite multiplication factor in comparison to Method 1 in the early stage of burnup, and that Method 2 becomes to overestimate the factor after a certain degree of burnup. This is because Method 2 overestimates the depletion rate of the gadolinia.