棒束内湍流流动特性的PIV与CFD研究

在压水堆燃料组件的定位格架下游,局部扰动沿流动方向逐渐衰减,流场最终趋于稳定。光滑棒束区冷却剂的湍流流动和交混特性是影响反应堆经济性和安全性的重要因素,有必要进行深入研究。本文采用粒子图像测速（PIV）与数值模拟(CFD)相结合的方法,对3×3小规模棒束内水的流动特性进行研究,得到了一阶平均流速以及二阶湍流统计信息。结果表明,中心子通道的速度明显高于棒间隙区,但轴向均方根速度呈现出相反的变化趋势。在相邻子通道横向速度梯度的作用下,棒束内出现了大尺度的流量脉动现象,且脉动波长随雷诺数的增加而增大。此外,实验得到的湍流交混系数较压水堆采用的Castellana公式预测值偏高10%左右,这一偏差随雷诺数的增加有减小的趋势。     

摇摆条件下典型通道间湍流的流动传热特性

利用Fluent软件分析了摇摆条件对典型四棒束间的湍流流体流动和传热特性的影响机理。摇摆运动会对棒束间流体的流动传热特性产生一定影响,但不会对绝热通道与加热通道内流体流动相似性产生影响。而当摇摆幅度较大时,径向附加力会使通道横截面上的参数分布发生显著的变化,进而影响流体的流动与传热特性。在摇摆条件下,随着P/D（棒间距/棒直径）的逐渐减小,尤其是小于1.1时,典型棒束间流体的流动传热特性发生明显变化。     

脉动流下棒束通道内流场与湍流特性的PIV实验研究

事故条件下路基核反应堆以及受到海洋条件附加惯性力影响的浮动核反应堆一回路冷却剂会处于非稳定流动状态,进而改变冷却剂的流动和传热特性,影响反应堆的安全运行。本文应用锁相粒子图像测速（PIV）以及折射率匹配技术分别对脉动流条件下有无定位格架棒束通道内瞬时速度进行了测量。实验结果表明：对于不带定位格架的棒束通道,加速使得靠近通道壁面附近流体速度变大,而靠近中心区域流体速度变小。此外湍流强度分量随流体加速而逐渐变小,随流体减速而逐渐增加。对于流向压力梯度驱动的周期性脉动流,横向脉动速度均方根分量u′滞后于流向脉动速度均方根分量v′,且二者都滞后于流速的变化;对于带定位格架的棒束通道,带有搅浑翼的定位格架强烈的交混作用极大地减小了流体加速度对棒束通道内速度分布和湍流强度带来的影响。实验结果有助于更加清晰地揭示脉动流在棒束通道中的作用机理。     

棒束通道内环状流气液界面行为及形成机理研究

棒束通道中环状流气液界面行为的研究,能为压水堆的事故处理和沸水堆电厂的正常运行提供数据和理论支撑。本研究针对3×3棒束通道中环状流气液波状界面形式进行记录与分析,绘制详细的环状流流型图,并针对其形成机理进行分析。结果表明：棒束通道中的环状流主要有搅混型、未全润湿、平滑边界型、单一波状流、包状扰动波、带状扰动波和带状扰动波叠加液相丧失7种形式;单一波状流是当气相速度较高、液相速度较低时,气液界面上发生的有固定波峰和波谷、以固定速度向上运动的流动形式,其现象可通过Kelvin-Helmholtz型不稳定性理论来解释;当液相流量升高或气相流量减少时,发生单一波状流界面失稳,界面能量增加,进入到包状扰动波或带状扰动波阶段;当能量超过1.6 kPa²/Hz时,界面能量超过底层液膜束缚能力,产生液相丧失型环状流。     

Benchmark Simulation of Turbulent Flow through a Staggered Tube Bundle to Support CFD as a Reactor Design Tool. Part I: SRANS CFD Simulation

Time-invariant and time-variant numerical simulations of flow through a staggered tube bundle array, idealizing the lower plenum (LP) subsystem configuration of a very high temperature reactor (VHTR), were performed. In Part I, the CFD prediction of fully periodic isothermal tube-bundle flow using steady Reynolds-averaged Navier-Stokes (SRANS) equations with common turbulence models was investigated at a Reynolds number (Re) of 1.8 × 10⁴, based on the tube diameter and inlet velocity. Three first-order turbulence models, standard k-ε turbulence, renormalized group (RNG) k-ε, and shear stress transport (SST) k-ω models, and a second-order turbulence model, Reynolds stress model (RSM), were considered. A comparison of CFD simulations and experiment results was made at five locations along (x, y) coordinates. The SRANS simulation showed that no universal model predicted the turbulent Reynolds stresses, and generally, the results were marginal to poor. This is because these models cannot accurately model the periodic, spatiotemporal nature of the complex wake flow structure.     

摇摆条件下子通道内湍流流体的数值分析

利用FLUENT软件分析了摇摆条件对典型四棒束间的湍流流体流动和传热特性的影响机理。摇摆运动会对棒束间流体的流动传热特性产生一定影响。RSM模型可以很好地描述摇摆条件下子通道内的参数分布。摇摆周期变化带来的径向附加力的变化不会对摩擦阻力系数、传热系数和Reynolds应力产生影响。在摇摆条件下,摩擦阻力系数、传热系数和Reynolds应力呈周期性变化,但最大摩擦阻力系数所在时刻并不固定,而最大传热系数却始终是在流速最大的时刻。     

有界域轴向流动中棒束流致振动和稳定性研究

基于Ｃｈｅｎ有界域静止流体中棒束流致振动数学模型,给出了棒束稳定分析的数值方法。作为应用研究,分析了有界域轴向流动中棒束（４根）流致振动的特性及稳定性,给出了不同条件下轴向及横向的振型。     

脉动流下棒束通道内相位差及瞬态流场研究

事故条件及海洋条件下反应堆处于非稳态工况,堆芯燃料组件内热工水力行为具有瞬变及多因素耦合特性,对反应堆的安全提出更高挑战,因此有必要对燃料组件内瞬态特性进行研究。本文通过测量棒状燃料组件内压降和流量之间延迟时间开展棒束通道脉动流条件下相位差研究,对比了相位差在不同振幅、不同流动状态下的变化特性,并分析了定位格架对脉动流相位差的作用特点。另外,基于粒子图像测速（PIV）技术开展了脉动流条件下棒束通道内流场分布特性研究,对比了相同流量条件下稳态工况与瞬态工况下流场分布差异,分析了主流具备不同加速度时棒束通道内流场分布特征。实验结果表明：定位格架可减小脉动流下棒束通道内相位差;棒束通道内流场演化滞后于主流量变化。实验结果有助于揭示燃料组件在非稳态条件下瞬态特性,并为燃料组件的设计和优化奠定基础。     

棒束通道内气液两相流流型的实验研究

常温、常压条件下,在7×7矩形截面棒束通道内进行了垂直向上气液两相流动实验,气液两相折算速度的变化范围分别为0.04~14 m/s和0.238~1.860 m/s。实验中用高速摄像仪对流型进行记录,观察到了泡状流、泡状-搅混流、搅混流和搅混-环状流4种流型,发现搅混流是主要流型,并对Hewitt流型图的界限进行了修正。分析实验数据发现,摩擦压降在泡状流和搅混流区域的变化是相反的。根据实验数据,参考前人的研究得到棒束通道中泡状流向搅混流转变的边界。     

棒束通道气液两相流流型识别及动力学特性分析

采集棒束通道实验台上气液两相流4种流型压差信号,计算4种流型的多尺度边际谱熵,对其进行流型识别及动力学特性分析。实验结果表明:多尺度边际谱熵能从整体上区分4种流型,从频域细节尺度定量揭示不同流型间的动力学特性;利用多尺度边际谱熵增率和谱熵均值联合分布可定量准确区分4种流型,对泡状-搅混流这种难以区分的过渡流型也有较好效果;与支持向量机结合具有运算速度快、识别率高的优点,准确率高达98.11%,适合流型的在线识别。     

棒束通道内定位格架的两相流动局部阻力实验研究

在常温、常压条件下,对竖直3×3棒束通道内定位格架的单相及两相局部阻力特性进行了实验研究。单相流动实验时,水雷诺数的变化范围为290~18 007;两相实验时,气相、液相表观速度变化范围分别为0.013~3.763m/s和0.076~1.792m/s。利用单相实验数据得到的定位格架局部阻力系数计算关系式,用两相实验数据对均相流模型中8种不同的两相等效黏度计算方法进行了评价。Rel9 000时,Dukler模型的预测效果最好;Rel≥9 000时,McAdams计算方法预测效果最好;基于所有数据,Dukler模型的计算值与实验值吻合最好,平均相对误差为29.03%。考虑了质量含气率、两相雷诺数及气液相密度的影响,对Rel9 000时的实验数据进行了拟合,得到的经验关系式的计算值与实验值符合较好。     

Characteristic of Two-phase Slanting Flow in Rod Bundle

Palladium membrane has been studied for sepration and purification of hydrogen isotopes because of its large permeability. In order to consider permeation of mixture of hydrogen isotopes, solubilities of protium and deuterium in palladium were studied in the temperature range of room temperature to 500°C using breakthrough method. It was observed that solubilities were represented by Sieverts' law and that the separation factor of protium-deuterium binary system was different from the isotope effect ratio. The ideal adsorbed solution theory by Myers and Prausnitz can be applied to estimate the separation factor of protium-deuterium binary system in palladium using the isotope effect ratio observed when protium and deuterium are handled independently. The permeation behavior of multi component hydrogen isotopes through palladium membrane is discussed applying observation on solubilities of this work.     

Analysis of Unsteady Turbulent Triple Jet Flow with Temperature Difference

Suitable analysis methodology is required to obtain detailed information about magnitude and frequency of temperature variation of flow field for the study of thermal stripping phenomena. The large eddy simulation (LES) is applied to analyze unsteady turbulent triple jet water flow which can be a direct cause of thermal stripping. Current analyses are performed with different sub-grid scale models, number of grids, time increments, and inlet temperature intensities to find the effects of these on prediction. Predicted results of the LES are compared with experimental results. The LES successfully produces a time history of turbulence variables, which can be used to evaluate magnitude and frequency of instantaneous temperature. The LES tends to predict higher levels of root mean square temperatures compared to those of an experiment, indicating very active mixing effect among triple jets. The LES is found to be able to provide reliable frequency information about temperature fluctuation. The different sub-grid scale models show no significant difference in prediction ability and other variations of the LES prediction show no significant difference in prediction either. However, cases using the fine grid and the small time increment are slightly better than others. Further study is desired with different levels of inlet temperature intensities and separate sub-grid scale models for temperature field.     

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。     

不同约束条件和几何参数对有界域轴向流动棒束稳定性的影响

基于有界域轴向流动中棒束流致振动数学模型和棒束稳定性的分析方法,作为应用研究,分析了棒束端约束条件和系统几何参数对系统失稳时临界流速的影响。     

Two-phase Flow Patterns in a Four by Four Rod Bundle

Air-water two-phase flow patterns in a four by four square lattice rod bundle consisting of an acrylic channel box of 68mm in width and transparent rods of 12mm in diameter were observed by utilizing a high speed video camera, FEP (fluorinated ethylene propylene) tubes for rods, and a fiberscope inserted in a rod. The FEP possesses the same refractive index as water, and thereby, whole flow patterns in the bundle and local flow patterns in subchannels were successfully visualized with little optical distortion. The ranges of gas and liquid volume fluxes, {J_G} and {J_L}, in the present experiments were 0:1 ? {J_L} < 2:0 m/s and 0:06 < {J_G} < 8:85 m/s, which covered typical two-phase flow patterns appearing in a fuel bundle of a boiling water nuclear reactor. As a result, the following conclusions were obtained: (1) the region of slug flow in the {J_G}-{J_L} flow pattern diagram is so narrow that it can be regarded as a boundary between bubbly and churn flows, (2) the boundary between bubbly and churn flows is close to the boundary between bubbly and slug flows of the Mishima and Ishii's flow pattern transition model, and (3) the boundary between churn and annular flows is close to the Mishima and Ishii's model.     

脉动流条件下棒束通道阻力特性研究

受海洋条件影响,浮动核反应堆（FNR）回路冷却剂会发生周期性流量波动现象,影响系统热工水力特性。为研究这一现象,对脉动流条件下5×5燃料棒束的阻力特性进行了试验研究。试验的周期平均雷诺数Re_ta＝0.8×10³～9×10³,脉动幅值Au＝0.2～0.8,无量纲频率ω′^1/2＝1.26～2.81。试验结果表明：脉动流条件下流体加速会导致瞬时阻力系数大于对应雷诺数的稳态值,减速会使瞬时阻力系数小于稳态值,且这一偏离值随流体流速的减小而增大。此外,在脉动流过程中,周期平均摩擦阻力系数λta和局部阻力系数kta都大于对应平均雷诺数下的稳态值。通过提出无量纲参数C_f＝λ_ta/λ_st和C_sg＝k_ta/k_st来评价脉动流对周期平均阻力系数的影响。C_f和C_sg随Au和ω′^1/2的增加而增加,随Re_ta的增加而减少。且在相同的脉动流参数下,C_sg小于C_f,说明流体波动对定位格架局部阻力的影响较小。最后,通过量纲分析,根据阻力系数的变化规律建立了预测λta和kta的计算关系式,得到了较好的预测结果。     

自然循环系统摇摆条件下棒束通道内传热特性研究

棒束燃料元件子通道间流体存在搅混与横向二次流,流动及阻力特性相较矩形通道、圆管等简单通道更为复杂。核动力舰船、船舶、小型浮动核电站等会受到海浪影响,经常处于倾斜、摇摆、垂荡等瞬变运动下。目前的相关研究多集中在低压工况的研究领域,高温高压自然循环运动条件下的研究较少。本文采用实验研究方法,对自然循环系统摇摆条件下棒束通道内流动传热特性进行了研究,获得了过冷沸腾和饱和沸腾两种条件下摇摆角度和摇摆周期对棒束壁面温度变化和传热系数的影响,并获得了摇摆周期内棒束通道内的传热系数计算关系式。结果表明,饱和沸腾传热系数变化比过冷沸腾的剧烈;在本文实验工况范围内,棒表面传热系数波动幅值随着摇摆幅度的增大而增大;摇摆条件下棒束通道过冷沸腾和饱和沸腾工况时均传热系数基本不变。     

棒束通道内两相流动摩擦阻力特性分析

常温常压下,对竖直3×3棒束通道内气液两相流动阻力特性进行了实验研究。利用所获得的实验数据,对8种典型的两相流动摩擦压降计算模型进行了评价。结果表明,均相模型在两相流速较高时精度较高,在两相流速较低时则偏差较大。分相模型中,Friedel模型和Lombodi-Pedrocchi模型不适用于本实验条件下棒束通道内气液两相流动摩擦压降的计算。Chisholm C模型、Zhang-Mishima模型、ChisholmB模型、Mishima-Hibiki模型及L.Sun模型的预测值与实验值的平均相对误差介于20%~30%之间。基于实验数据,通过修正ChisholmC模型的C系数,给出一个新的修正模型,其计算值与实验值符合良好。