含绕丝棒束低流速时阻力特性的实验研究

钠冷快堆含绕丝棒束组件低流速时的摩擦阻力特性,是设计钠冷快堆非能动事故余热排出系统的重要参数。使用水作为测量介质,采用改进的液柱测压方法,准确测量了一个有机玻璃材质37棒绕丝棒束组件雷诺数Re=200～1 100时的摩擦阻力特性。结果表明,被测量组件从层流向湍流转捩的临界Re为370。组件的入口段长度随着流速的增加而增大,随着流动开始向湍流转变而减小。现有的绕丝棒束摩擦阻力系数经验公式中,UCTD公式与实验值最接近：在层流区,UCTD公式高估了约7%,在层流向湍流转换区,UCTD公式计算值与实验值基本一致。同时,UCTD和CTS公式还高估了组件从层流向湍流转捩的临界Re。     

带绕丝燃料组件在铅铋介质下的阻力特性实验研究

基于KYLIN-II热工强迫循环实验回路,对CLEAR-I单盒燃料组件1:1模型组件在铅铋介质中的流动阻力特性进行实验研究。研究表明:组件整体压降实验值与设计值吻合较好,相对偏差在6%以内。对绕丝棒束段的摩擦阻力系数与Novendstern、Rehme公式进行对比,Novendstern模型更适用于本实验棒束结构的压降计算;基于雷诺相似准则与前期水介质下的阻力系数对比,发现相同雷诺数下水介质下的阻力系数明显偏大,其原因为相同雷诺数下绕丝在水介质中引起的二次横流强度大于铅铋介质下的情况。     

一种适用于钠冷快堆绕丝棒束组件热工水力特性分析的多孔介质模型

为准确预测钠冷快堆堆芯三维热工水力参数分布同时降低计算资源需求,基于表征体元概念建立了针对绕丝棒束组件的三维多孔介质模型,根据组件几何结构特点将冷却剂与固体壁面间的相互作用力分解为分布式阻力,引入包含湍流搅混传热、流体导热和燃料棒导热的有效传热系数模型刻画组件的径向传热。采用日本东芝公司核能工程实验室37棒液态钠冷却绕丝棒束组件实验进行模拟计算,数值计算结果与实验结果对比发现,基于论文提出的多孔介质模型可以在多种工况下较好地复现实验结果。因此,本研究提出的多孔介质模型可用于钠冷快堆绕丝棒束组件三维热工水力参数分布预测。     

快堆带绕丝棒束组件低雷诺数下的水力特性分析

低雷诺数(Re)流动存在于正常运行或事故停堆工况的各类组件中,对于快堆的安全运行具有重要意义。利用CFX程序对低Re下的中国实验快堆不同类型的带绕丝棒束组件的水力特性进行了分析。结果表明,通过利用1个螺距的带绕丝棒束组件计算得到的低Re下的水力特性与实验结果以及Engel关系式符合较好。通过利用4个螺距的带绕丝棒束组件计算结果表明,绕丝产生的横向流动使组件6个壁面上压力分布有所不同,但在流动充分发展时,每个面轴线方向的压降按螺距均匀分布,从而进行带绕丝棒束组件水力特性测量时,需在组件同一面上按照整数倍螺距来布置测点,才能避免由于横向流动对测量带来的影响。     

快堆带绕丝棒束组件低雷诺数下的水力特性分析

低雷诺数(Re)流动存在于正常运行或事故停堆工况的各类组件中,对于快堆的安全运行具有重要意义。利用CFX程序对低Re下的中国实验快堆不同类型的带绕丝棒束组件的水力特性进行了分析。结果表明,通过利用1个螺距的带绕丝棒束组件计算得到的低Re下的水力特性与实验结果以及Engel关系式符合较好。通过利用4个螺距的带绕丝棒束组件计算结果表明,绕丝产生的横向流动使组件6个壁面上压力分布有所不同,但在流动充分发展时,每个面轴线方向的压降按螺距均匀分布,从而进行带绕丝棒束组件水力特性测量时,需在组件同一面上按照整数倍螺距来布置测点,才能避免由于横向流动对测量带来的影响。     

基于双区域模型的钠冷快堆组件子通道分析程序的开发与验证

子通道分析程序是钠冷快堆堆芯热工水力设计和安全分析的重要工具。本文为计算和分析钠冷快堆组件在径向均匀与倾斜功率分布工况下的热工水力特性,利用双区域绕丝交混模型开发了一款适用于钠冷快堆组件分析的子通道程序SPLICA,并与FFM2A 19棒束实验数据与WARD 61棒束实验数据进行了对比验证。由于本文开发的子通道分析程序SPLICA使用了详细的绕丝交混模型,与经过二次开发后的COBRA程序的计算结果相比,对于FFM2A实验SPLICA程序计算得到的结果与实验结果符合得更好。这两个实验数据的验证结果证明了本文开发的子通道分析程序的准确性以及对高流量工况和低流量工况均具有良好的适用性。本程序能为钠冷快堆组件热工水力分析提供有效的设计和研究手段。     

钠冷快堆乏燃料组件自然循环冷却瞬态过程的数值模拟研究

应用Fluent程序,对处于氩气中的钠冷快堆乏燃料组件自然循环冷却瞬态过程进行了三维数值模拟。计算获得了乏燃料组件内部冷却剂通道和外部区域的热工水力学现象及变化规律。结果表明:利用标记区域分割方法,将燃料棒间隙网格划分为绕丝网格和绕丝周边流体域网格,能在棒束区生成高质量结构化网格;在氩气自然循环冷却瞬态过程中,棒束区内子通道氩气流量增加速度落后于边子通道,内子通道升温更快;乏燃料组件棒束区温度在轴向呈现中心高、边缘低的分布特征;为避免包壳温度超过设计值,乏燃料组件处于氩气中的时间不宜超过6min。     

钠冷快堆燃料组件热工水力特性数值模拟与分析

利用CFD程序CFX,分别对7、19、37、61根棒组成的三角形排列螺旋绕丝定位的钠冷快堆燃料组件棒束通道进行了热工水力特性的分析研究,并将结果与子通道程序SuperEnergy进行了对比验证。重点考察了棒束通道轴向流动分布、横向流交混效应及子通道轴向温升,分析了定位绕丝的影响。结果表明,绕丝对棒束通道的横向流交混效应、轴向流动分布及子通道温升有着重要影响,且随棒束的增多,通道内的流动趋向复杂化,轴向流动不均匀性有升高趋势。     

全流态工况下绕丝棒束内的摩擦压降模型研究

为准确预测液态铅铋在燃料组件棒束内截面的摩擦压降特性,需选取合适的摩擦压降模型。针对8种不同的绕丝棒束内摩擦压降模型,采用统计分析的方式评估模型的适用性,研究不同模型在不同流态范围内实验数据的预测准确性。分析结果表明：摩擦系数不仅与棒束数量（Nr）和节径比（P/D）有关,还与螺径比（H/D）有关;在层流范围内BBDD模型和本文模型与实验数据较为吻合;在过渡流范围内BBDD模型、CTD模型和本文模型与实验数据较为吻合;在湍流范围内Rehme模型、UCTD模型和本文模型与实验数据较为吻合。因此,本文提出的模型适用于全流态的燃料组件棒束内截面的摩擦压降预测。     

含绕丝棒束内横向流动的可视化实验与数值模拟研究

螺旋绕丝是第4代先进核反应堆燃料组件的定位装置之一,冷却剂在绕丝作用下发生定向交混和周期性横流,是影响燃料元件包壳温度的重要因素,有必要进行深入研究。本文采用粒子图像测速法对含绕丝7棒束内水的横向流动进行实验测量,得到了横截面整体速度分布和局部流动特性,并利用STAR CCM+软件进行了稳态数值模拟,分析了无量纲横向流速的变化规律。结果表明,棒束内存在整体环流和若干局部涡流,大尺度涡出现在棒和内壁附近,小尺度涡出现在棒和绕丝附近。随着雷诺数的增大,横向流动规律基本一致,但速度大小呈线性增长趋势。湍流模型敏感性分析表明,雷诺应力-椭圆混合模型对流场的预测与实验数据最为接近。横向流动具有明显的周期性,对于所选定的棒束结构,最大横向流速约为轴向流速的25%,且在绕丝经过棒间隙时出现突变。     

Hydraulic characteristics of wire-wrapped rod bundles

Existing hydraulic data such as pressure fields, velocity fields, friction factors, flow split and sweeping flows were reviewed and summarized. In addition equations were suggested to calculate subchannel friction factors, flow split and flow sweeping. It was concluded that sufficient data and analysis exist to generate a complete physical model to characterize turbulent flow in wire-wrapped rod bundles; there are inadequate data to construct a physical model to describe laminar and natural circulation flow. Potential hydraulic problems related to rod bundle dimensional tolerances, non-nominal and/or time-dependent pressure drop characteristics should be resolved.     

基于PIV技术的低雷诺数下棒束通道流场研究

基于粒子图像测速(PIV)技术开展了低雷诺数(Re)条件下5×5棒束通道内充分发展段的流场可视化研究,试验Re从310～12296内选择了22组工况进行研究。试验结果表明:在低Re下,棒束通道内部的相对速度梯度较大,随着Re的上升,棒束通道内速度趋向于均匀化分布;通过阻力特性观察到的棒束通道中转捩相对于圆管较为模糊,转捩Re为900左右;在低Re效应的影响下,无量纲速度均方根随Re的增大而减小,而在转捩Re附近出现了无量纲速度均方根随Re的增大而增大的现象;此外该试验可以用于验证湍流模型对于不同Re的适用性。     

棒束通道内混合对流传热实验研究

以自然循环下堆芯内可能会发生的低流量传热为研究背景,对5×5棒束通道内的混合对流传热现象进行了实验研究。实验压力为6 MPa, 质量流量为25~150 kg/(m2·s),热流密度为25~300 kW/m2,实验雷诺数Re为1000~30000,浮升力参数Bo*为2×10-7~3×10-3。实验发现,随着Bo*的增大,棒束通道内传热产生先弱化后强化的趋势。浮升力对棒束通道内传热造成影响的起始点为Bo*=3.5×10-6,当Re >15000时,浮升力依然可对传热造成弱化现象。基于实验数据,提出了适用于棒束通道的混合对流经验关系式。      

定位格架对流场影响的可视化实验研究

进行可视化实验,研究AFA-2G5×5定位格架对流场的影响。采用染色法研究定位格架顶端叶片 的交混作用,用白色玻璃球作为示踪剂研究棒束内的三维流场分布,二维激光多普勒测速仪(LDV)测量定位 格架上下游的横向和轴向速度分布。实验还得到了定位格架的压降特性和光棒的摩擦阻力特性。     

Laser doppler measurements of flow in a rod bundle

A two component laser doppler velocimeter with polarized beams and frequency shift was used to measure the turbulent flow field for axial flow between the rods of a nine rod, square pitch rod bundle. Parameters measured include mean axial and lateral velocities, turbulence intensities and the friction factor. The axial velocities for 10000 to 40000 Reynolds number are slightly higher than those reported by Rowe. The maximum lateral velocities measured are about 1% of the bulk velocity; somewhat larger than suggested by earlier authors. Axial and lateral turbulence intensities are larger than those in pipe flows.     

Effects of buoyancy on laminar vertical upward flow friction factors in cylindrical tubes

The coupled energy and momentum equations were solved for fully developed vertical upward laminar flow in a cylindrical tube. A simple engineering correlation which agreed well with the analytical solution was obtained. In addition, an effect was obtained and incorporated into a general engineering correlation. Comparison of the general correlation with the existing data was adequate. If the results for a cylindrical tube can be applied to typical wire-wrapped rod bundles in a LMFBR the use of an increased friction factor to account for buoyancy effects in laminar flow is not justified because the maximum value of the Grashof—Reynolds number ratio is small.     

Turbulent flow simulation in a wire-wrap rod bundle of an LMFBR

The pressure drop and heat transfer characteristics of wire-wrapped 19-pin rod bundles in a nuclear reactor subassembly of liquid metal cooled fast breeder reactor (LMFBR) have been investigated through three-dimensional turbulent flow simulations. The predicted results of eddy viscosity based turbulence models (k-?, k-ω) and the Reynolds stress model are compared with those of experimental correlations for friction factor and Nusselt number. The Re is varied between 50,000 and 150,000 and the ratio of helical pitch of wire wrap to the rod diameter is varied from 15 to 45. All the three turbulence models considered yield similar results. The friction factor increases with reduction in the wire-wrap pitch while the heat transfer coefficient remains almost unaltered. However, reduction in the wire-wrap pitch also enhances the transverse flow velocity in the cross-sectional plane as well as the local turbulence intensity, thereby improving the thermal mixing of coolant. Consequently, the presence of wire wrap reduces temperature variation within each section of the subassembly. The associated reduction in differential thermal expansion of rods is expected to improve the structural integrity of the fuel subassembly.     

Mixed convective flow penetration in vertical channels

The primary purpose of the study is to investigate the factors relevant to the decay heat removal system in pool-type liquid metal reactors which are designed to remove decay heat in a passive way utilizing natural circulation. The reactor geometry is simulated by a vertical rod bundle channel connected to an upper plenum. Penetration of cold fluid from the upper plenum into the rod bundle channel is investigated experimentally and analytically with water as a working fluid. Three correlations to predict the onset of penetration, the penetration depth, and the ratio of penetrating to forced flowrate were developed. The correlations were found to agree well with experimental results for the range of Reynolds number in which experimental data were obtained.     

Heat transfer, momentum losses and flow mixing in a 61-tube bundle with wire-wrap

Friction factors and heat transfer coefficients were obtained in the laminar and turbulent regions for a 61-tube wire-wrapped hexagonal bundle in a water flow loop. Circumferential static pressure and temperature profiles of tubes, and the flow patterns produced by injection of dye at the periphery of the bundle revealed a strong local effect of the wire-wrap. The increase in heat and momentum transfer resulting from the wire-wrap was more pronounced in the laminar region than in the turbulent region. Correlations for the friction factors and Nusselt numbers were developed from the data and compared with the literature.