十字焊点对定位格架水力特性影响的数值研究

作为定位格架重要的结构特征之一,其内条带间的十字焊点的形状与定位格架的强度及水力特性密切相关。为深入研究该十字焊点形状对定位格架水力特性的影响规律,以5×5燃料组件定位格架为研究对象,采用ANSYS CFX12.1对燃料棒束通道内的流动现象进行数值模拟研究,得到了通道内的流场分布。研究结果表明:增加十字焊点直径能削弱格架下游近格架区域子通道内冷却剂的涡流强度以及子通道间的搅混强度,同时增强格架下游远格架区域子通道内的涡流强度以及子通道间搅混强度;增加十字焊点直径对格架下游子通道内的搅混强度影响较小;定位格架的形状阻力系数随十字焊点直径的增大而增加。以上结果说明采用较大直径的十字焊点可使定位格架下游区域的换热能力趋于均衡,从而使堆芯温度分布更加均匀,但同时也会产生较大的压力损失。     

定位格架压降关系式及CFD数值模拟研究

现有格架压降经验关系式中缺少对格架本身结构的描述,导致压降估计不准确。为准确估计格架的压力损失,利用商用计算流体动力学(CFD)软件,从基础研究的角度出发,分别探索刚凸位置、搅混翼排列的边距以及子通道间的互相搅混等对压降及下游流场的影响。在拟合格架压降经验关系式时,需要加入更多的描述格架自身结构的几何参数。在格架设计中要根据不同的格架设计目标和设计功能,针对性地优化刚凸位置、搅混翼排列及子通道的之间的互相搅混。     

2×2棒束通道格架搅混翼横向流场PIV实验研究

以2×2放大棒束通道格架模型为基础,利用粒子图像测速(PIV)对格架搅混翼引起的燃料组件棒束通道内横向流场特性进行实验研究。测量流体经过格架搅混翼后不同位置的横向速度发展情况,比较折弯角分别为20°、25°、30°、35°、40°和45°时横向流场的变化情况,给出雷诺数对横向流场的影响。获得4个典型雷诺数(Re为33000、36000、40000、45000)下的流场特性。结果表明,Re和搅混翼折弯角度的改变,都会显著影响棒束通道内横向流动。     

带MVG和MSMG的5×5全长棒束单相流场和温度行为数值分析

定位格架作为燃料组件的关键部件之一，直接影响到燃料组件的热工性能。本文对带结构格架（MVG）和跨间搅混格架（MSMG）的5×5全长加热棒束单相流场和温度场采用计算流体力学（CFD）程序进行数值分析研究，获得该特征棒束组件出口二次流场以及温度场分布特性。研究表明，定位格架下游流场受定位格架和距离的影响，定位格架上游流场对下游二次流几乎无影响，定位格架导致流体强烈的横向二次流，增强了流体和加热棒之间的换热能力，使得棒束子通道截面流体温度更加均匀。与5×5全长棒束出口子通道温度的实验数据对比分析表明，获得的计算模型可以较好地分析该型棒束组件结构温度场行为。      

棒束通道内定位格架搅混特性PIV可视化研究

定位格架作为燃料组件中重要的组成部件之一，不仅在结构上固定燃料棒，而且在燃料组件内热工水力性能同样显著，特别是对工质的搅混性能直接关系到反应堆的经济性和安全性，因此有必要对燃料组件内定位格架搅混特性进行研究。本文通过粒子图像测速（PIV）技术开展了棒束通道内定位格架上下游流场的可视化研究，对比了有无格架棒束通道内流场的分布特征，定量分析了定位格架对棒束通道流场搅混的贡献。对不同流速下定位格架下游横纵速度的沿程变化特性进行研究，发现了不同流速作用下定位格架对横向、轴向速度的促进和抑制规律。另外，通过速度均方根对下游的湍流特性进行了评估。实验结果可为数值计算提供全场的数据验证，并可为定位格架设计和优化提供基础。     

5×5定位格架棒束通道阻力特性研究

采用数值方法对5×5定位格架棒束通道的阻力特性进行研究。采用常用的减小弹簧、刚凸高度,使其与燃料棒间留有微小间隙的方式对格架进行几何建模,发现计算得到局部阻力系数明显小于实验值,分析原因并参考面接触的思路,提出改进的格架几何模型,并采用不同湍流模型进行数值模拟,得出SST模型计算的结果与试验值符合很好。利用改进的模型研究搅混翼及其他部件的阻力特性,发现搅混翼在格架局部阻力系数中所占的比重很小,但其引发的横向流使格架下游的摩擦阻力增加。     

棒束通道定位格架沸腾临界特性数值研究

为研究核反应堆中定位格架及搅混翼对沸腾临界现象产生的影响，本文采用计算流体动力学（CFD）分析方法，探讨了棒束通道中定位格架的数目、位置和搅混翼的角度对于沸腾临界现象的影响。结果表明:定位格架会对主流流动产生阻力，同时定位格架数目越多，沸腾临界发生的温度也越高，但将定位格架布置在沸腾临界发生位置时，则可有效改善壁面传热环境并降低沸腾临界发生时的峰值温度。搅混翼的存在则会有效降低加热面附近空泡份额，改善传热环境，但搅混翼角度过大时会导致沸腾临界提前发生。      

棒束燃料组件横流的远心PIV测量方法

压水堆棒束燃料组件通常在定位格架上设有搅混翼片,以促进横向搅混。因而,定位格架下游的横流是评判格架性能的重要依据。针对定位格架下游横流可视化测量的挑战,为粒子图像测速(Particle Image Velocimetry,PIV)系统设计了远心光路,有效地降低了图像的畸变。此外,针对粒子图像测速对光强均匀度的要求,在测量区域采用了氟化乙烯丙烯共聚物(Fluorinated Ethylene Propylene,FEP)管作为实验工质水的折射率补偿材料,消除了由于固体材料折射率过大导致的类似凸透镜的聚光效果。通过标定实验及流场测量实验证明,该测量方法能够获取5×5棒束格架下游完整截面的横向流速及漩涡结构。实验观测发现:在5Dh位置翼片搅混导致的横向流场依然很强烈,其强度会随着距离的增加而逐渐减弱。     

压水堆燃料棒束通道内过冷沸腾分析

使用Fluent14.5两流体模型中的RPI(Rensselaer Polytechnic Institute)壁面沸腾模型,对堆芯燃料棒束通道内过冷沸腾现象进行数值模拟,得到了通道内的流场、温度场以及空泡份额的分布,分析了定位格架和搅混翼的存在对热工水力特性的影响。数值结果表明,格架的存在会造成很大的压降,而搅混翼会对流场、温度场和空泡份额分布产生显著影响;RPI壁面沸腾模型的模拟结果与Bartolemei试验数据符合很好。     

定位格架新型搅混翼设计研究

定位格架是影响燃料组件热工水力性能的重要部件,其搅混翼对流体存在搅混作用。本文主要针对定位格架搅混翼对流体的搅混作用,采用计算流体力学(CFD)方法研究子通道内部及子通道之间流动搅混较为薄弱的环节。研究表明,增大搅混翼外形尺寸能增强格架的搅混能力,带辅翼的新型搅混翼设计能有效弥补主翼对流动搅混的不对称性,增强格架子通道内部的涡旋搅混能力,优化布置的辅翼形式,不过多减弱子通道之间的横向流搅混作用,且有利于搅混效果的沿程发展,同时还兼顾考虑了由此带来的格架压降增大。     

压水堆子通道欠热沸腾数值验证及交混翼研究

为改善压水堆交混翼格架在欠热沸腾工况下的热工水力特性,以子通道为研究对象验证了所使用的欠热沸腾数值模型在不同工况下的有效性。基于已验证的数值模型,对含不同偏折角交混翼格架的子通道模型在不同工况下进行了两相流数值模拟,研究交混翼及其偏折角对子通道中两相流动、传热及气泡分布的影响。结果表明：交混翼在增大压降的同时明显强化了冷却剂的交混、降低了近壁面气泡份额、提高了换热效率,且在一定范围内偏折角越大影响越明显。相对较高的气泡份额将导致更大的压力损失、减弱冷却剂的交混、降低传热效率。当交混翼偏折角达25°时,继续增大其偏折角对降低近壁面气泡份额和提高传热效率的作用不再明显,反而造成压降的快速增大,因此建议其偏折角在25°左右。     

棒束及格架布置对燃料组件搅混特性影响的实验研究

以CPR1000核电机组使用的格架组装的5×5棒束燃料组件为对象,开展了多组全长棒束燃料组件搅混特性实验,重点分析了冷-热棒布置形式、格架布置形式等几何参数对燃料组件搅混特性的影响规律,实验结果表明,冷-热棒中心对称布置时的燃料组件热扩散系数更接近真值;跨间搅混格架对燃料组件总体热扩散系数有较小增强作用,但对于棒束压降的贡献很低。      

Comparison of thermo-hydraulic performances of large scale vortex flow (LSVF) and small scale vortex flow (SSVF) mixing vanes in 17 × 17 nuclear rod bundle

Spacer grids in the nuclear fuel rod assembly maintain a constant distance between rods, secure flow passage and prevent the damage of the rod bundle from flow-induced vibration. The mixing vanes attached to the spacer grids generate vortex flows in the subchannels and enhance the heat transfer performance of the rod bundle. Various types of mixing vanes have been developed to produce cross flows between subchannels as well as vortex flows in the subchannels.The shapes of the mixing vane have been improved to generate larger turbulence and cross flow mixing. In the present study, two types of large scale vortex flow (LSVF) mixing vanes and two types of small scale vortex flow (SSVF) mixing vanes are examined. SSVF-single is conventional split type and SSVF-couple is split type with different arraying method. LSVF mixing vane has different geometry and arraying method to make large scale vortex. 17 × 17 rod bundle with eight spans of mixing vanes is simulated using the IBM 690 supercomputer. The FLUENT code and IBM supercomputer is employed to calculate the flow field and heat transfer in the subchannels.Turbulence intensities, maximum surface temperatures of the rod bundle, heat transfer coefficients and pressure drops of the four kinds of mixing vanes are compared. LSVF mixing vanes produced higher turbulence intensity and heat transfer coefficient than SSVF mixing vanes. Consequently, LSVF mixing vane increases the thermal efficiency and safety of the rod bundle.     

湍流模型对5×5格架棒束通道流动传热数值模拟影响分析

同一软件工具采用不同湍流模型进行燃料组件格架棒束通道CFD分析时会得到不同的数值结果,本文采用ANSYS CFX软件,建立了包含典型5×5格架的棒束通道CFD模型,研究了涡粘和雷诺应力两大类6种典型湍流模型对燃料组件压降与换热特性数值结果的影响,计算了压降和Nu分布结果与相似的实验结果进行对比,通过分析3个典型搅混效果评价因子,探讨了搅混翼流动与换热的内在影响关系,同时对比了不同湍流模型对结果的影响。通过与相似实验数据对比分析,认为雷诺应力模型较适宜计算本文所研究的定位格架及棒束通道内流动传热特性。     

Evaluation of a numeric procedure for flow simulation of a 5 × 5 PWR rod bundle with a mixing vane spacer

The fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles arranged in a regular square configuration by spacer grids placed along its length. The presence of the spacer grids promote two antagonist effects on the core: a desirable increase of the local heat transfer downstream the grids and an adverse increase of the pressure drop due to the constriction on the coolant flow area. Most spacer grids are designed with mixing vanes which cause a cross and swirl flow between and within the subchannels, enhancing even more the heat transfer performance in the grid vicinity. The improvement of the heat transfer increases the departure from the nucleate boiling ratio, allowing higher operating power in the reactor. Due to these important thermal and fluid dynamic features, experimental and theoretical investigations have been carried out in the past years for the development of spacer grid design. More recently, the Computational Fluid Dynamics (CFD) using three dimensional Reynolds Averaged Navier Stokes (RANS) analysis has been used efficiently for this purpose. Many computational works have been performed, but the appropriate numerical procedure for the flow in rod bundle simulations is not yet a consensus. This work presents results of flow simulations performed with the commercial code CFX 11.0 in a PWR 5 × 5 rod bundle segment with a split vane spacer grid. The geometrical configuration and flow conditions used in the experimental studies performed by Karoutas et al. were assumed in the simulations. To make the simulation possible with a limited computational capacity and acceptable mesh refinement, the computational domain was divided in 7 sub-domains. The sub-domains were simulated sequentially applying the outlet results of a previous sub-domain as inlet condition for the next. In this study the k-ε turbulence model was used. The simulations were also compared with those performed by Karoutas et al. in half a subchannel and In et al. in one subchannel computational domains. Comparison between numerical and experimental results of lateral and axial velocities along of the rod bundle show good agreement for all evaluated heights downstream the spacer grid. The present numerical procedure shows better predictions than Karoutas et al. model especially further from the spacer grid where the peripheral subchannels have more influence in the average flow.     

Evaluation of a numeric procedure for flow simulation of a 5 × 5 PWR rod bundle with a mixing vane spacer

The fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles arranged in a regular square configuration by spacer grids placed along its length. The presence of the spacer grids promote two antagonist effects on the core: a desirable increase of the local heat transfer downstream the grids and an adverse increase of the pressure drop due to the constriction on the coolant flow area. Most spacer grids are designed with mixing vanes which cause a cross and swirl flow between and within the subchannels, enhancing even more the heat transfer performance in the grid vicinity. The improvement of the heat transfer increases the departure from the nucleate boiling ratio, allowing higher operating power in the reactor. Due to these important thermal and fluid dynamic features, experimental and theoretical investigations have been carried out in the past years for the development of spacer grid design. More recently, the Computational Fluid Dynamics (CFD) using three dimensional Reynolds Averaged Navier Stokes (RANS) analysis has been used efficiently for this purpose. Many computational works have been performed, but the appropriate numerical procedure for the flow in rod bundle simulations is not yet a consensus. This work presents results of flow simulations performed with the commercial code CFX 11.0 in a PWR 5 × 5 rod bundle segment with a split vane spacer grid. The geometrical configuration and flow conditions used in the experimental studies performed by Karoutas et al. were assumed in the simulations. To make the simulation possible with a limited computational capacity and acceptable mesh refinement, the computational domain was divided in 7 sub-domains. The sub-domains were simulated sequentially applying the outlet results of a previous sub-domain as inlet condition for the next. In this study the k–ε turbulence model was used. The simulations were also compared with those performed by Karoutas et al. in half a subchannel and In et al. in one subchannel computational domains. Comparison between numerical and experimental results of lateral and axial velocities along of the rod bundle show good agreement for all evaluated heights downstream the spacer grid. The present numerical procedure shows better predictions than Karoutas et al. model especially further from the spacer grid where the peripheral subchannels have more influence in the average flow.     

燃料组件5×5格架多跨模型CFD模拟方法研究

本文详细描述了某典型燃料组件5×5格架模型CFD分析的几何模型简化、网格划分、求解及后处理等过程。在5×5结构单跨模型上研究了弹簧刚突对搅混特性及压降的影响,并采用简化弹簧刚突的5×5格架模型实现了包含11层格架的多跨模型计算。单跨模型计算结果表明,弹簧刚突结构强化了横向流动,利于换热,Nu提高了8%,但弹簧刚突格架模型较简化弹簧刚突模型压降损失增加了40%。多跨模型计算得到了多层格架全程流动换热特性,为燃料组件自主研发中定位格架数量及布置的设计优化以及DNB预测计算提供了有效的CFD分析方法。     

Flow Characteristics in Spacer Grids Measured by Rod-embedded Fiber Laser Doppler Velocimetry

Precise measurement of velocity in fuel bundles is required to improve the thermal-hydraulic properties of Pressurerized Water Reactor (PWR) spacer grids. To better understand the cross-flow characteristics in rod bundles for developing spacer grids, we used the rod-embedded fiber laser Doppler velocimetry (rod LDV) to measure the flow velocities inside the spacer grid flow channels. As the result of measurement, we found that the flow distribution inside the spacer grid depends on the local flow resistance of the grid straps and is clearly affected by the presence of a mixing vane. We also clarified the relationship between cross-flow velocity in the fuel bundle downstream of the spacer grid and the axial flow inside the spacer grid.     

Thermal-hydraulic performance analysis of a subchannel with square and triangle fuel rod arrangements using the entropy generation approach

The present paper discusses entropy generation in fully developed turbulent flows through a subchannel,arranged in square and triangle arrays. Entropy generation is due to contribution of both heat transfer and pressure drop. Our main objective is to study the effect of key parameters such as spacer grid, fuel rod power distribution,Reynolds number Re, dimensionless heat power ω, lengthto-fuel-diameter ratio λ, and pitch-to-diameter ratio ξ on subchannel entropy generation. The analysis explicitly shows the contribution of heat transfer and pressure drop to the total entropy generation. An analytical formulation is introduced to total entropy generation for situations with uniform and sinusoidal rod power distribution. It is concluded that power distribution affects entropy generation.A smoother power profile leads to less entropy generation.The entropy generation of square rod array bundles is more efficient than that of triangular rod arrays, and spacer grids generate more entropy.     

冷却剂与含格架燃料棒束多场耦合分析

燃料棒束作为压水堆燃料组件的组成部分，其热工和结构特性直接关系到反应堆的安全。本文利用ANSYS WORKBENCH软件分析了冷却剂在5×5含定位格架燃料棒束通道内流动的分布，采用冷却剂与燃料棒束多场耦合的方式研究了燃料棒束的流动传热特性和结构形变特性。结果表明：定位格架扰动冷却剂形成横向二次流并在下游棒束间形成绕流；多场耦合条件下二次流峰值速度和平均速度均小于单流场的；二次流与燃料棒的热应力使棒束发生形变，功率和流动分布的不均匀导致形变在轴向和径向的不均匀；相较于无格架情况，定位格架的存在使冷却剂的搅混流动更加明显，冷却剂对燃料棒冲击增大；在有、无定位格架两种情况下棒束形变均很小，可保持原本结构的稳定。