子通道分析中的湍流交混研究综述

在子通道分析中,湍流交混是冷却剂通道间横向交混的重要组成部分,是由于流体脉动时自然涡团扩散引起的非定向交混。湍流交混的强弱程度将影响通道的局部热工参数,从而影响临界热流密度的预测,是反应堆热工水力设计与分析重点关注的对象。本文针对湍流交混的相关研究进行了综述,包括机理与模型、湍流交混系数、实验方法、计算流体动力学(CFD)方法和子通道软件中的模型等,可作为自主化燃料组件设计和自主化子通道分析软件开发的参考。     

燃料组件精细化定位格架模型开发及评价

为提高燃料组件子通道内两相局部参数预测的准确性,本文基于分布式阻力方法建立精细化定位格架模型,选用合适的摩擦阻力表达式,对格架上的交混翼进行精细化建模,采用Carlucci湍流交混模型计算湍流交混速率,引入阻塞因子计算由定位格架引起的湍流交混效应,并将建立的精细化定位格架模型植入子通道分析程序（ATHAS）,对压水堆子通道和棒束实验（PSBT）基准题进行计算分析。结果表明,本文开发的精细化定位格架模型能够提高燃料组件子通道内空泡份额和温度分布的预测准确性,为棒束通道流场、焓场计算和临界热流密度（CHF）预测奠定了基础。      

堵塞条件下紧密栅湍流交混特性研究

开展堵塞工况下紧密栅内流体子通道间隙湍流交混研究,对事故工况下燃料组件热工水力行为的预测具有重要意义。本文采用CFD方法对紧密栅内堵塞工况的流体流动现象进行了模拟,模拟结果与相关文献结果吻合较好。进一步对比分析了不同堵塞工况下,堵塞段及堵塞下游的速度场、涡结构以及湍流交混系数分布。所得不同堵塞工况下的横向与轴向湍流交混系数变化规律,可为子通道分析程序的参数设置提供参考。     

棒束子通道湍流交混特性的数值模拟研究

为了提高核反应堆系统的经济性和安全性,本文采用CFD方法对棒束子通道间湍流交混效应进行研究。对子通道建模,选取SST k-ω模型进行计算,完成了网格敏感性分析。采用类比浓度计算法与间隙湍流热流法对湍流交混系数进行计算。计算结果表明：雷诺数较小时,单相湍流交混系数随雷诺数的增大而增大;当雷诺数达到一定值时,单相湍流交混系数近似为定值;采用类比浓度计算法与间隙湍流热流法计算所得的湍流交混系数无太大差别。本文拟合得到了适用于单相工况的湍流交混系数计算公式。     

铅铋冷却绕丝燃料组件横流特性分析

准确预测绕丝棒束通道内的横向流动特性是开展铅铋冷却快堆热工水力安全分析的基础。本文采用数值模拟的方法分析了液态铅铋工质下单绕丝和多绕丝燃料组件内的横流特性。分析结果表明,单绕丝组件的中心子通道横流流速最大不超过主流流速的19%,且横流方向和二次流中心随着高度周期性变化;单绕丝组件中,当绕丝与子通道交界面重合或垂直时,中心子通道界面横向流量和横流交混指数趋于零或达到峰值;在单绕丝组件结构一定的情况下,横流交混指数在湍流区对Re不敏感,而与组件结构参数存在较大相关性;多绕丝组件中心子通道界面上的横流存在两个相反的流向。     

方形子通道内超临界流体流动传热CFD分析

国际上对超临界水冷堆进行了大量的研究,但对其堆芯内超临界流体流动传热特征的认识还十分欠缺.本研究采用CFX软件对典型超临界反应堆燃料组件子通道内的超临界热工水力特征进行了数值分析.研究了流动参数、边界条件和节径比(P/D)对子通道间交混现象和传热特性的影响.计算结果表明:燃料组件外围壁面子通道比内部子通道的湍流交混强烈;稠密栅格的湍流交混比宽栅格的湍流交混小.当P/D>1.2后,P/D比对湍流交混影响不再明显.研究还发现,在拟临界点附近区域,出现湍流交混系数的突变.     

液态铅铋合金在绕丝燃料棒组件子通道间湍流交混数值模拟

液态铅铋合金（LBE）是第四代液态金属核反应堆候选冷却剂,由于LBE热物性具有一定的特殊性,亟待对LBE在燃料组件子通道中的流动与传热过程开展研究。本文对LBE在带绕丝燃料棒组件中湍流流动进行数值模拟与分析,将燃料棒壁面温度的数值模拟结果与响应的实验数据相比较,2者具有较高的吻合度,说明数学模型及数值结果具有较高的可靠性与准确性;使用湍流交混系数β表征LBE在不同子通道间、不同燃料棒间隙宽度与燃料棒直径比（S/D）结构下的湍流交混情况,结果表明,不同子通道间β波动程度具有差异性,β的大小与S/D呈负相关。基于不同S/D与雷诺数的计算结果,拟合出不同子通道间β关联式,为绕丝燃料棒三角形排列方式的燃料组件子通道分析程序开发提供交混模型。      

5×5螺旋十字型棒束组件阻力与交混特性实验研究

本文对5×5螺旋十字型棒束(HCF)组件进行热工水力实验,获得了HCF组件的阻力系数和交混系数。测量了螺旋十字型棒束组件的沿程压降,并拟合了阻力系数关系式。基于能量平衡法对HCF组件的交混特性进行了分析。将低温水直接注入棒束组件的子通道中,通过测温导管将T型热电偶固定在子通道的中心位置,并测量了各子通道内的水温分布。HCF组件内的横向交混由湍流交混和流动后掠组成,定义等效交混系数来分析HCF组件内的横向交混率。HCF组件的等效交混系数不随雷诺数的增加而明显变化,其均值为0.019。将等效交混系数输入子通道分析程序Cobra-tf中,计算了子通道内的水温分布。结果表明,水温分布的实验值和计算值符合良好,平均偏差为0.16 ℃。     

燃料组件单相交混系数试验研究

在高温高压大型热工试验装置上,采用5×5全长棒束装配法国X型格架,开展燃料组件交混系数试验研究.试验设计了专门的测温组件,成功实现子通道出口温度场的精确测量.利用子通道分析程序FLICAⅢF与试验数据相配合,共同确定燃料组件的交混系数值.试验所得交混系数值为0.065,与原设计值0.066十分接近.试验同时验证了交混系数主要由燃料组件结构决定,热工参数影响极小.     

各类子通道单相湍流交混的实验研究

用化学示踪法测量了三角形排列元件组件内各类子通道间单相湍流交混的流率,得到了它们相应的关系式。实验包括:中央子通道四种壁距直径比P/d=1.20,1.33,1.38,1.505;壁区子通道四种壁距直径比δ_w/d=0.0556,0.098,0.172和0.256;子通道的雷诺数范围为(1～4)×10~4。实验结果表明:中央和壁区子通道间单相湍流交混流率是棒间距、子通道当量直径及雷诺素的函数,并随棒间距增加有明显增加。本文得到其关系式。实验结果和其他研究者的结果做了比较,发现比较符合。     

A modified equilibrium void distribution model applicable to subchannel-scale vapor–liquid cross flow model for conventional square and tight lattice BWR fuel bundles

As a part of the advanced subchannel code development project sponsored by Ministry of Economy, Trade and Industry, Japan, this paper describes improvement of the equilibrium void distribution model that is a main part of the vapor–liquid cross flow model.The three-component cross flow (TCCF) model is defined as the present framework that separates contributions of diversion, turbulent mixing and void drift. The Lahey's void settling model is introduced to express the latter two components. Based on the high-resolution air–water database and other published data of steam-water tests, general trends of vapor–liquid cross flow processes are examined. It can be assumed that subchannel void distributions are dominated by the three major effects, i.e. the fluid dynamic effect, the geometrical effect and the narrow gap effect.The equilibrium void distribution model is modified to include the above-mentioned three effects. Three characteristic parameters are assigned for each of the three effects and they are identified experimentally as functions of the void fraction. Multi-dimensional lattice geometries are incorporated based on the two-dimensional flow network model. The network equation is constructed by mapping the equilibrium void balance problem into the force-deflection problem. The resultant models are verified based on equilibrium void distribution data obtained by Sadatomi and Kawahara.     

The effect of turbulent mixing models on the predictions of subchannel codes

In this paper, the predictions of the COBRA-IV and ASSERT-4 subchannel codes have been compared with experimental data on void fraction, mass flow rate, and pressure drop obtained for two interconnected subchannels. COBRA-IV is based on a one-dimensional separated flow model with the turbulent intersubchannel mixing formulated as an extension of the single-phase mixing model, i.e. fluctuating equal mass exchange. ASSERT-4 is based on a drift flux model with the turbulent mixing modelled by assuming an exchange of equal volumes with different densities thus allowing a net fluctuating transverse mass flux from one subchannel to the other. This feature is implemented in the constitutive relationship for the relative velocity required by the conservation equations. It is observed that the predictions of ASSERT-4 follow the experimental trends better than COBRA-IV; therefore the approach of equal volume exchange constitutes an improvement over that of the equal mass exchange.     

Nuclear magnetic resonance: A new tool for the validation of multiphase multidimensional CFD codes

Turbulent transport models and data in bubbly flows are briefly reviewed since they play an important role in the modeling of boiling flows in forced convection. Shortcomings of earlier measurements of the eddy diffusivity by NMR (Lemonnier and Leblond, 2007b) are analyzed and a new procedure is presented which is now consistent with the procedure of Gatenby and Gore (1994) developed for single-phase turbulent flow characterization. The newly estimated eddy diffusivity agrees now with that previously obtained by Serizawa et al. (1975b) with a thermal method and that of the model of Sato and Sadatomi (1981). This procedure also provides the liquid velocity fluctuation RMS and the Lagrangian correlation time of velocity fluctuations. In addition, the same NMR technique provides also the area-averaged liquid velocity and void fraction. Bubbly flow data up to transition to slug flow are provided which also agree with existing drift-flux models (Ishii and Hibiki, 2006). It is finally discussed how the NMR method can be extended to local measurements and may provide a fully non-intrusive diagnostic in two-phase flows and which is not limited to bubbly flow.     

Assessment of the interchannel mixing model with a subchannel analysis code for BWR and PWR conditions

The influence of the interchannel mixing model employed in a traditional subchannel analysis code was investigated in this study, specifically on the analysis of the enthalpy distribution and critical heat flux (CHF) in rod bundles in BWR and PWR conditions. The equal-volume-exchange turbulent mixing and void drift model (EVVD) was embodied to the COBRA-IV-I code. An optimized model of the void drift coefficient has been devised in this study as the result of the assessment with the two-phase flow distribution data for the general electric (GE) 9-rod and Ispra 16-rod test bundles. The influence of the subchannel analysis model on the analysis of CHF was examined by evaluating the CHF test data in rod bundles representing PWR and BWR conditions. The CHFR margins of typical light water nuclear reactor (LWR) cores were evaluated by considering the influence on the local parameter CHF correlation and the hot channel analysis result. It appeared that the interchannel mixing model has an important effect upon the analysis of CHFR margin for BWR conditions.     

垂直上升两相流漂移流模型研究

漂移流模型在两相流空泡率计算中处于非常重要的地位,长期以来,研究者对模型中分布参数及漂移速度的确定持不同的观点.本文采用理论分析与实验研究相结合的方法,总结了分布参数和漂移速度的一般规律,提出了垂直上升两相流漂移流模型分布参数和漂移速度必须满足的限制条件,根据理论分析以及实验数据的验证,得出了漂移流模型推荐关系式.     

Two-phase turbulent mixing and buoyancy drift in rod bundles

This paper describes the development of generalized relationships for single- and two-phase intersubchannel turbulent mixing in vertical and horizontal flows, and lateral buoyancy drift in horizontal flows.The relationships for turbulent mixing, together with a recommended one for void drift, have been implemented in a subchannel thermalhydraulics code, and assessed using a range of data on enthalpy migration in vertical steam–water flows under BWR and PWR diabatic conditions. The intent of this assessment was to optimize these relationships to give the best agreement with the enthalpy migration data for vertical flows. The optimized turbulent mixing relationships were then used as a basis to benchmark a proposed buoyancy drift model to give the best predictions of void and enthalpy migration data in horizontal flows typical of PHWR CANDU¹ reactor operation under normal and off-normal conditions.Overall, the optimized turbulent mixing and buoyancy drift relationships have been found to predict the available data quite well, and generally better and more consistently than currently used models. This is expected to result in more accurate calculations of subchannel distributions of phasic flows, and hence, in improved predictions of critical heat flux (CHF).     

Correlations for predicting single phase and two-phase flow pressure drop in pebble bed flow channels

An experimental study was conducted on the pressure drop of the single phase and the air–water two-phase flow in the bed of rectangular cross sections densely filled with uniform spheres. Three kinds of glass spheres with different equivalent diameters (3 mm, 6 mm, and 8 mm) were used for the establishment of the test sections. The Reynolds number in the experiment ranged from a dozen to thousands for the single-phase flow and from hundreds to tens of thousands for the two-phase flow. In the present flow-regime model, the bed was subdivided into a near-wall region and a central region in order to take the wall effect into account to improve the prediction at low tube-to-particle diameter ratios. Improved correlations are obtained based on the previous study to consider the single-phase flow pressure drops for finite pebble beds with spherical particles and nonspherical particles by fitting the coefficients of that equation to both the database and the present experiment. The correlation is consistent with the observed physical behavior which explains its comparatively good agreement with the experimental data. A new empirical correlation for the prediction of two-phase flow pressure drops was proposed based on the gas phase relative permeability as a function of the gas phase saturation and the void fraction. The correlation fit well for both experimental data of spherical particles and nonspherical particles.     

Prediction of turbulent mixing rates of both gas and liquid phases between adjacent subchannels in a two-phase slug-churn flow

This paper presents a slug-churn flow model for predicting turbulent mixing rates of both gas and liquid phases between adjacent subchannels in a BWR fuel rod bundle. In the model, the mixing rate of the liquid phase is calculated as the sum of the three components, i.e. turbulent diffusion, convective transfer and pressure difference fluctuations between the subchannels. The components of turbulent diffusion and convective transfer are calculated from Sadatomi et al.'s [Nucl. Eng. Des. 162 (1996) 245–256] method, applicable to single-phase turbulent mixing, by considering the effect of the increment of liquid velocity due to the presence of gas phase. The component of the pressure difference fluctuations is evaluated from a newly developed correlation. The mixing rate of the gas phase, on the other side, is calculated from a simple relation of mixing rate between gas and liquid phases. The validity of the proposed model has been confirmed with the turbulent mixing rates data of Rudzinski et al. [Can. J. Chem. Eng. 50 (1972) 297–299] as well as the present authors.     

Flow redistribution due to void drift in two-phase flow in a multiple channel consisting of two subchannels

Void drift in two-phase flow is studied experimentally using a geometrically simple, vertical channel consisting of two interconnected subchannels. Data on the flow redistributions of both air and water along the channel axis are obtained and presented for the following two multiple channels: one with two circular subchannels of different cross-sectional area and the other with two identical circular subchannels. The data are analysed by a simple one-dimensional subchannel code taking account of the effects of void drift and turbulent mixing between subchannels, i.e. incorporating both the void-settling model of Lahey et al. and a term similar to that in the COBRA code in the momentum equation. The flow redistribution process can be explained by the analysis.