应急排气管道对主烟囱中速度及气体混合的影响

应用计算流体力学(CFD)方法,模拟内部的应急排气管道存在与否对主烟道内气体组分混合的影响情况。以速度及示踪气体浓度的变异系数(COV)表征截面混合均匀性,对比研究了高风速(约13.1 m/s)、中风速(约8.2 m/s)、低风速(约0.56 m/s)三种典型工况。结果表明:主烟道内风速13.1 m/s,无内部管道可使...     

放射性气载流出物取样代表性分析

为获取核设施放射性气载流出物单点连续监测取样位置,提出基于随机轨道模型(DRW)的气-固多相湍流耦合方法求解代表性取样区域。借助k-epsilon湍流模型模拟连续相,并引入离散颗粒模型(DPM)模拟离散相,建立基于DRW模型的排风管道内流道气-固多相湍流耦合计算模型,计算了核设施气载流出物在管道内流道流场分布规律,分析了内流道流体气旋角、气流速度、示踪气体浓度、气溶胶粒子浓度与管道高度间的关联关系。分析结果表明,随着截面高度的增加,气旋角、气流速度变异系数(COV)、示踪气体浓度COV及示踪气体浓度最大值与平均值的偏差逐渐降低并趋于稳定,气溶胶粒子浓度COV在截面6与截面8满足取样代表性要求;基于计算流体动力学方法可快速地确定出代表性取样位置,为气载流出物单点取样现场试验提供了理论参考依据。     

扩散角对文丘里管内湍流影响的试验研究

为研究扩散角对文丘里管内湍流的影响,采用立体粒子图像测速技术分别对扩散角度为10°、12.5°、15°以及20°的文丘里管扩散段区域进行了测量,得到了平均速度分布,并通过瞬时速度场的统计分析得到了扩散段湍动能分布情况。研究表明,不同扩散角度的文丘里管扩散段内平均速度在截面直径方向成轴对称的单峰分布,湍动能在截面直径上成轴对称的双峰分布,在各试验工况下扩散段内均发生流动分离现象。随扩散角度增加,湍动能峰值增加,主流区径向宽度未发生变化,分离流区径向宽度增加,但对分离流区所占比例的影响较小,高湍动能区变宽;随着雷诺数的增加,湍动能峰值增加,主要由轴向雷诺应力引起,分离流区所占比例略有降低,但主流区和分离流区分布变化较小。此研究为高雷诺数不同角度的文丘里管流场研究提供了实验基础。      

5×5定位格架棒束通道内三维流场研究

采用混合网格技术、SST k-ω湍流模型、改进的速度-压力耦合算法SIMPLEC求解雷诺时均的连续性方程、动量方程,得到格架内各截面的速度场和压力场。计算结果表明：在定位格架的影响下,通道内产生了强烈的横向流动;横向速度呈抛物线分布,轴向速度分布在通道内趋于均匀;阻力系数随进口雷诺数的增大而减小。将速度分布和阻力系数分布的预测值与试验值进行了对比,两者吻合较好。     

空气-水在垂直非圆截面通道内流型研究

采用可视化方法研究了水力直径分别为15mm和10mm的两种正方形截面、14.43mm的三角形截面以及14mm的圆形截面通道内空气-水垂直上升流动,表观气速0.04～80m/s,表观水速0.001～6m/s.观察到了泡状流、弹状流、块状流、环状流和弥散泡状流等常见流型.此外,在表观气速很大而表观水速很小时,在非圆截面通道内发现了爬动流,证实了非圆截面直通道内存在"二次流"现象,且对气-液两相流动的相分布有较大影响,证明截面形状对两相流流型及其转变具有重要影响.由实验得到了流型转变界限,并首次获得了包括爬动流的两相流流型图.比较本文的实验结果及与前人的研究结果对比发现,水力直径的大小对两相流流型的转变具有一定影响.     

超临界水四棒束传热数值分析

超临界水冷堆(SCWR)开发的关键是棒束内超临界水(SCW)的热工水力特性。本文针对超临界水四棒束流动传热实验进行CFD数值模拟,SSG湍流模型的计算结果与实验结果吻合良好。分析结果表明,流动方向对棒束截面内流量分布有显著影响。与下降流相比,尽管上升流时棒束间流动搅混较弱,但上升流时棒束截面流量及壁面周向温度分布更加均匀,加热棒壁面温度更低。可见,棒束横截面上的流量分布是影响加热棒壁面流动传热的主要因素。     

基于四方程模型的LBE环管湍流换热数值研究

为计算液态铅铋（LBE）在环管内不同加热环境下的湍流换热,基于开源计算流体力学程序OpenFOAM开发了四方程模型求解器4eqnFoam。将LBE在平板和圆管内的预测结果与直接数值模拟结果和实验结果进行对比,验证了求解器的有效性。基于该求解器,分别计算了LBE在外壁绝热内壁加热以及内外壁面等热流加热环管内不同雷诺数下的湍流换热量。结果表明：随着雷诺数的增加,两种加热条件下的无量纲温度脉动、雷诺热流、湍流热扩散作用增大,而平均湍流普朗特数减小;当雷诺数增加到一定程度时,平均湍流普朗特数变化不明显。基于4eqnFoam求解器,可为计算LBE热工水力现象提供更多参考。     

压力容器环形下降段内含硼溶液流动混合特性的数值模拟分析

发生堆芯应急冷却安注时,外部注入的含硼冷却剂与稀释水团将在环形下降段内发生混合,含硼冷却剂与稀释水团混合不均匀可能导致堆芯重返临界。本文基于Fluent 18.0对环形下降段内的流动混合特性进行分析。横截面的速度分布显示,入口截面的水平方向速度随周向位置的增加而显著衰减,而环形下降段下部区域横截面的速度分布趋于平缓;三维流线图显示,流体进入压力容器后在环腔内壁发生剧烈碰撞,随后绕环形下降段呈放射状流动。通过自定义硼酸溶液,并模拟其与稀释水团之间混合,数值结果与相关的实验研究结果较为一致;三维浓度分布显示,雷诺数较低时入口硼酸溶液将停滞在环形下降段上部空间,增加入口雷诺数有利于搅混均匀。     

气液两相流工况下核主泵的正转全特性研究

在冷却液流失事故(LOCA)事故发生期间,核主泵将处于两相混合运行状态。主要对核主泵的正转全工况不同含气率冷却介质的泵水力性能、流道内部气体体积分布情况及流体流态进行研究,并采用计算流体力学(CFD)模拟计算与气液两相流试验进行验证。研究发现:在正转逆流制动工况,核主泵的扬程曲线随含气率增加整体向下偏移,但其变化规律基本相同。在正转水泵工况和正转正流制动工况,随着流量增加,含气率对核主泵扬程特性的影响逐渐减小,且同流量下核主泵的扭矩和冷却剂介质密度成较为明显的正比关系。     

环形截面螺旋通道内层流换热热力性能数值模拟

在恒壁温工况下,对旋转720°环形截面螺旋通道内三维层流换热的热力性能进行数值模拟.研究雷诺数为200～1000、无量纲螺距为0.1～0.2、曲率范围为0.1～0.3、在内环加热外环绝热情况下螺旋通道内不同截面上的温度场分布和速度场分布以及雷诺数、曲率和无量纲螺距对轴向不同截面上平均努谢尔特数和平均摩擦系数的影响.研究结果表明:在人口阶段,二次流作用可以忽略,随着转角增大,二次流作用加强,且垂直于轴向截面的最大速度向通道的外侧移动;轴向截面平均努谢尔特数和轴向截面平均摩擦系数随着雷诺数、曲率和螺距的变化呈现不同的规律,并且和曲率相比,螺距对传热和流动性能的影响程度相对较小.     

Large eddy simulation on the flow characteristics of an argon thermal plasma jet

Large eddy simulations based on the CFD software OpenFOAM have been used to study the effect of Reynolds number and turbulence intensity on the flow and mixing characteristics of an argon thermal plasma jet.Detailed analysis was carried out with respect to four aspects:the average flow field,the instantaneous flow field,turbulence statistical characteristics and the self-similarity.It was shown that for the argon thermal plasma jet with low Reynolds number,increasing the turbulence intensity will increase the turbulent transport mechanism in the mixing layer rather than in the jet axis,leading to the faster development of turbulence.The effect of the turbulent transport mechanism increases with increasing Reynolds number.However,the characteristics of flow and mixing are not affected by turbulence intensity for high Reynolds number situations.It was also found that the mean axial velocity and mean temperature in the axis of the turbulent thermal plasma jet satisfy the self-similarity aspects downstream.In addition,decay constant K is 1.25,which is much smaller than that(5.7-6.1)of the turbulent cold gas jet and has nothing to do with the Reynolds number or turbulence intensity in the jet inlet.     

不同棒束结构稠密栅元通道内的湍流CFD研究

采用URANS（UnsteadyReynoldsAveragedNavierStokes）方法对不同棒束结构稠密栅元通道（P/D=1.001～1.2）内的湍流流动进行CFD模拟。研究分析了不同Re（Re=5000~215000）的湍流流动的主流速度、壁面剪应力、湍动能等参数。研究表明：在较稠密的棒束（P/D<1.1）通道内,P/D的变化对子通道内主流速度和剪应力分布均有较大影响。本文的模拟结果也验证了在达到临界P/D前（即使δ/D<0.011）,交混因子Y和δ/D成反比关系。对于固定的棒束结构（P/D=1.062）,当Re达到一定值（Re=9600）时,子通道内主流速度和剪应力分布对Re的变化不敏感。     

定位格架下游湍流特性测量研究

在子通道雷诺数为6 600、13 200、26 400和39 600下,使用粒子成像测速仪对5×5棒束分流型交混翼定位格架下游横向和纵向流动进行测量。平均速度和湍流脉动速度均方根的实验结果最大不确定度低于1%的主流平均速度。格架下游二次流结构经历了交混翼脱落涡结构耗散、剪切产生双涡结构、双涡结构向单涡结构的转变及单涡结构沿程衰减过程,横向平均速度和湍流脉动速度均方根沿程变化均受涡结构演进影响。格架近场湍流统计量迅速衰减;格架远场湍流统计量缓慢衰减,流动趋于光棒束充分发展流动。横向流动受雷诺数效应和格架交混效应共同影响。     

On the transport mechanisms in simulated heterogeneous rod bundle subchannels

Experimental results are presented on fully developed turbulent flow through simulated heterogeneous rod bundle subchannels. The emphasis of this study is on the universality of the cross-gap turbulence convection transport with respect to symmetric versus asymmetric subchannels. The flow passage was formed by a rod asymmetrically mounted in a trapezoidal duct. The Reynolds number based on the equivalent hydraulic diameter and bulk average axial velocity is 26 300. The measurements include mean axial velocities, r.m.s. values of the fluctuating velocity components and the energy density spectra. The results demonstrate the existence of an unusual region near the asymmetric rod-to-wall gap characterized by high levels of axial turbulence intensity with a remarkably different type of distribution compared with a normal boundary layer. It is also shown that the strength of the cross-gap transport is subchannel geometry dependent. The distributions of wall shear stress and turbulence kinetic energy indicate that mean convection by secondary flow is also an important transport mechanism that should be taken into account in the analysis of momentum/heat transfer in rod bundle subchannels.     

Numerical Investigation of Gas Flow Distribution and Thermal Mixing in Helically Coiled Tube Bundle

In this study, we carried out the numerical simulation of gas flow across a helically coiled tube bundle, which is fitted in the annular space between a central spine and an outer casing. We focused on the effect of clearances at the inner and outer radial boundaries on the gas flow distribution and thermal mixing in the tube bundle. The conservation equations of mass, momentum and energy were numerically solved by computational fluid dynamics. It was demonstrated from the numerical simulation results that (i) the gas flow distribution in the tube bundle is very sensitive to clearances at the inner and outer radial boundaries, and even a very small variation of clearances would lead to a considerable change in the average velocity profile, which correspondingly leads to a great deviation of the gas flow distribution away from the original one; (ii) the clearance effect on thermal mixing is not as strong as that on gas flow distribution;(iii) the Reynolds number has little effect on the gas flow distribution and thermal mixing, the latter of which is in agreement with the results of Achenbach experiments.     

Numerical investigations of thermal mixing performance of a hot gas mixing structure in high-temperature gas-cooled reactor

A numerical simulation study was performed to clarify the thermal mixing characteristics of coolant in the core bottom structure of the high-temperature gas-cooled reactor(HTR). The flow field and temperature field in the hot gas chamber and the hot gas duct of the HTR were obtained based on the commercial computational fluid dynamics(CFD) program. The numerical simulation results showed that the helium flow with different temperatures in the hot gas mixing chamber and the hot gas duct mixed intensively, and the mixing rate of the temperature in the outlet of the hot gas duct reached 98 %. The results indicated many large-scale swirling flow structures and strong turbulence in the hot gas mixing chamber and the entrance of the hot gas duct, which were responsible for the excellent thermal mixing of the hot gas chamber and the hot gas duct. The calculated results showed that the temperature mixing rate of the hot gas chamber decreased only marginally with increasing Reynolds number.     

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

In Part II, we described the unsteady flow simulation and proposed a modification of a traditional turbulence flow model. Computational fluid dynamics (CFD) simulations of an isothermal, fully periodic flow across a tube bundle using unsteady Reynolds averaged Navier-Stokes (URANS) equations, with turbulence models such as the Reynolds stress model (RSM) were investigated at a Reynolds number of 1.8 × 10⁴, based on the tube diameter and inlet velocity. As noted in Part I, CFD simulation and experimental results were compared at five positions along (x; y) coordinates. The steady RANS simulation showed that four diverse turbulence models were efficient for predicting the Reynolds stresses, and generally, SRANS results were marginal to poor, using a consistent evaluation terminology. In the URANS simulation, we modeled the turbulent flow field in a manner similar to the approach used for large eddy simulation (LES). The time-dependent URANS results showed that the simulation reproduces the dynamic stability as characterized by transverse oscillatory flow structures in the near-wake region. In particular, the inclusion of terms accounting for the time scales associated with the production range and dissipation rate of turbulence generates unsteady statistics of the mean and fluctuation flow. In spite of this, the model implemented produces better agreement with a benchmark data set and is thus recommended.     

Experimental tests on the applicability of a radioactive tracer technique for measuring coolant mixing in nuclear reactor fuel subassemblies

A previously reported radioactive tracer method for measuring coolant mixing hot channel factor is developed here. Feasibility of the technique is demonstrated with a test section simulating part of a reactor sub-channel. The test section consists of a tube containing three hollow rods simulating the fuel rods, mounted in a small hydraulic loop. Tests were carried out by injecting a ³²P activated phosphate into the main flow at Reynolds number ranging from 20 000 to 70 000. The concentration of the tracer was measured by detecting the β-rays of ³²P with three windowless Geiger-Müller counters, placed inside the hollow rods, β-particles reach the counters through openings in various axial positions along the length of the rods, covered by a thin stainless steel foil. Measured values of the concentration are reported and corresponding values of coolant cross-flow are calculated.     

基于CFD方法的铅铋冷却燃料棒束的热工水力特性分析

铅铋冷却快堆作为第4代反应堆候选之一具有安全性高等特点，研究其在正常工况下的热工水力特性具有重要意义。本文基于商用计算流体力学（CFD）软件STAR-CCM+，使用流固耦合的方法对带有绕丝结构的19棒束铅铋组件进行数值分析，探究了质量流量、功率等边界条件对组件内部流动传热特性的影响。模拟计算结果表明：CFD方法在子通道中心温度和壁面温度预测上与实验结果取得了较好的一致。同时，绕丝结构的存在使得子通道之间存在周期性的横向交混，并使得棒束表面温度呈现震荡。随质量流量的增加，子通道间横向交混增大。功率变化对通道间的横向交混速度的影响较小，冷却剂温度的横向分布无明显差异。