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。      

三角形棒束内铅铋湍流普朗特数模型研究

为准确预测低普朗特数流体在燃料组件棒束子通道内的传热特性,需选取合适的湍流普朗特数模型。针对5种不同的湍流普朗特数模型,基于三角形棒束换热关联式,研究采用剪切应力传输（Shear Stress Transfer,SST）k-ω湍流模型,分析不同的棒束子通道结构,并与液态铅铋实验验证的换热关联式计算结果进行对比,分析不同棒径与节径比条件下各种湍流普朗特数模型的适用性。分析研究结果表明,整体湍流普朗特数模型不仅与雷诺数Re、贝克莱数Pe有关,还与节径比P/D有关;在节径比1.3～1.7范围内Kays学者提出的局部湍流普朗特数模型模拟结果与Mikityuk关系式计算值较为吻合;各种湍流普朗特数模型均有最佳的节径比适用范围。因此,相关模型能够用于不同节径比条件下三角形棒束子通道内铅铋传热特性的预测。     

铅铋冷却快堆含绕丝燃料组件子通道程序开发与验证

由于铅铋冷却剂流动传热现象的复杂性,准确计算铅铋冷却含绕丝燃料组件的冷却剂和包壳温度是液态金属冷却快堆燃料组件热工分析的重点。本文基于集总参数法对守恒方程进行求解,开发了适用于铅铋冷却快堆的子通道分析程序,对液态铅铋在棒束燃料组件中的摩擦阻力模型、湍流交混模型和对流换热模型进行了适用性分析,并对7棒束大涡模拟和19棒束含绕丝传热实验进行了对比验证。结果表明：包壳和冷却剂温度的最大相对误差低于5%。程序能较好完成铅铋冷却含绕丝燃料组件的热工水力计算,可为铅铋冷却快堆设计提供支持。     

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。     

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。     

压水堆主泵飞轮周围间隙流中泰勒涡传热特性的数值研究

反应堆冷却剂主泵飞轮周围的间隙空间充满流体。飞轮按额定工况速度旋转时,间隙内流体作周向剪切流动的同时产生强烈的湍流泰勒涡二次流动,改变了飞轮间隙流的传热特性。本文采用不同的湍流模型对湍流泰勒涡进行了模拟,雷诺应力模型的模拟结果与现存实验结果最为接近。数值模拟显示,主泵飞轮圆柱面间隙中充满排列规则的周期泰勒涡对,飞轮端面间隙中出现覆盖全端面的扁环形涡胞。飞轮圆柱表面的当地热流密度和努塞尔数与泰勒涡一样呈明显的周期性变化规律。圆柱面泰勒涡对和端面涡胞增强了飞轮区域的传热能力,对飞轮和周围承力部件的温度分布产生重要影响。     

CFX中湍流模型用于分析超临界水传热的适用性评价

通过两组典型实验数据,对商业软件CFX的12种湍流模型用于模拟超临界水竖直向上流动传热的性能进行评价。研究结果表明：强迫对流时,BSL代数应力模型与实验结果符合最好,但各模型间差异均不大;混合对流时,基于壁面函数的ε类型湍流模型不能模拟传热恶化趋势,自动壁面处理的ω类型湍流模型能模拟出传热恶化的趋势,但各模型预测结果和实验结果相差较大。评价结果表明近壁面的处理方式对模拟结果影响很大。此外,基于湍流普朗特数模拟湍流热流密度及未考虑密度脉动对传热的影响均是导致不能正确模拟超临界水传热行为的因素,建议对湍流模型进行改进。     

液态铅铋合金管内流动传热特性研究

为研究液态铅铋合金的流动传热特性,建立了相应的实验台架,并开展了传热特性试验,获得了1组针对液态铅铋合金的传热关系式。同时使用Fluent程序对圆管内铅铋合金的流动换热进行了模拟计算,以研究不同湍流普朗特数模型和不同湍流模型的选取对计算结果的影响。根据计算结果,探讨了不同湍流普朗特数模型对计算结果的影响,并得到了不同Peclet数下推荐使用的物理模型。     

液态金属钠在圆管内传热特性数值模拟研究

为研究液态金属钠在不锈钢材料表面流动时的湍流传热特性,在已有实验研究的基础上,提出了k-ε模型下的湍流普朗特数Pr_t模型,并使用Fluent程序对圆管内的液态金属钠在不锈钢材料表面流动时的传热特性进行了计算。理论设计值与已有实验结果进行对比,二者符合较好。根据本文提出的Pr_t模型,可较为精确地计算液态金属钠在不锈钢材料表面流动时的传热特性。     

稠密栅元棒束内流动行为的CFD数值模拟

国内针对稠密栅元组件内流体的流动和传热特征展了大量的实验研究,但目前仍缺乏对稠密栅元通道内冷却剂流动特性的全面认识.本文对矩形和三角形稠密栅元通道内的空气湍流流动进行了数值研究.结合实验数据,系统地验证了涡粘性和雷诺应力两类湍流模型模拟稠密栅元内流动特征的适用范围.结果表明:SSG雷诺应力模型对流动有较好的模拟,但在棒壁窄缝处的计算结果与实验数据存在较大的差距;在y+<20时,SSG模型对近壁面区域网格的疏密不敏感;在y+较小时,二阶ω模型出现数值震荡.     

Investigation on turbulent heat transfer to lead–bismuth eutectic flows in circular tubes for nuclear applications

Since many years, the Forschungszentrum Karlsruhe has been working on the research and development of an accelerator driven sub-critical system (ADS) cooled by lead–bismuth eutectic (LBE). Although various numerical tools for thermal hydraulics have been established at the Forschungszentrum Karlsruhe, reliably validated physical models related to turbulent heat transfer in LBE flows are still missing. Especially, physical models on heat transfer and turbulent Prandtl number have to be re-evaluated in LBE conditions to improve the reliability of numerical tools. In the present paper, review and assessment of the existing physical models are made. Computational fluid dynamics (CFD) analysis is carried out for circular tube geometries. Based on the assessment of the existing models and the CFD results achieved, recommendations are made on correlations of heat transfer and turbulent Prandtl number for numerical applications to LBE flows.     

数值堆热工流体程序CVR-PACA验证及典型应用

谱元方法是一种高精度的数值计算方法,采用该方法开发了数值堆高精度热工水力并行CFD计算程序CVR-PACA。应用CVR-PACA对单棒光棒通道湍流流场、3×3光棒棒束湍流流场、Matis-H压水堆棒束通道基准题、19棒带绕丝组件通道湍流流场进行了仿真计算。通过与实验测量值对比,研究定量验证了大涡模拟(LES)模型及非稳态雷诺时均(URANS)模型对各类棒束通道流场预测的准确性。算例在建模过程中采用网格分裂技术实现了复杂几何的纯六面体网格划分,用于支撑谱元方法计算。研究较为全面地积累了高精度谱元方法模拟流场流动及换热的建模经验,获取了各类棒束通道内丰富的流动和换热细节,获得的建模经验能更加精准有力地指导相关设计的优化改进。     

Turbulence-induced Heat Transfer in PBMR Core Using LES and RANS

This paper introduces the results of numerical simulations on flow fields and relevant heat transfer in the pebble bed reactor (PBR) core. In the core, since the coolant passes a highly complicated random flow path with a high Reynolds number, an appropriate treatment of the turbulence is required. A set of simple experiments for the flow over a circular cylinder with heat transfer was conducted to finally select the large eddy simulation (LES) and k-ω model among the considering Reynolds-averaged Navier-Stokes (RANS) models for PBR application. Using these models, the PBR cores, whose geometries were simplified to the body-centered cubical (BCC) and face-centered cubical (FCC) structures, were simulated. A larger pressure drop, a more random flow field, a higher vorticity magnitude and a higher temperature at the local hot spots on the pebble surface were found in the results of the LES than in those of RANS for both geometries. In cases of the LES, the flow structures were resolved up to the grid scales. Irregular distributions of the flow and local heat transfer were found in the BCC core, while relatively regular distributions for the FCC core. The turbulent nature of the coolant flow in the pebble core evidently affected the fuel surface temperature distribution.     

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.     

Investigation on heavy liquid metal cooling of ADS fuel pin assemblies

In the framework of accelerator driven sub-critical reactor systems heavy liquid metals are considered as coolant for the reactor core and the spallation target. In particular lead or lead bismuth eutectic (LBE) exhibit efficient heat removal properties and high production rate of neutrons.However, the excellent heat conductivity of LBE-flows expressed by a low molecular Prandtl number of the order 10⁻² requires improved modeling of the turbulent heat transfer. Although various models for thermal hydraulics of LBE flows are existing, validated heat transfer correlations for ADS-relevant conditions are still missing. In order to validate the sub-channel codes and computational fluid dynamics codes used to design fuel assemblies, the comparison with experimental data is inevitable.Therefore, an experimental program composed of three major experiments, a single electrically heated rod, a 19-pin hexagonal water rod bundle and a LBE rod bundle, has been initiated at the Karlsruhe Liquid metal Laboratory (KALLA) of the Karlsruhe Institute of Technology, in order to quantify and separate the individual phenomena occurring in the momentum and energy transfer of a fuel assembly.     

管内过冷流动沸腾CFD模型参数敏感性研究

采用CFD方法对燃料组件进行过冷流动沸腾数值模拟研究是反应堆热工水力分析的一项重要内容。本研究使用STAR CCM+基于欧拉双流体模型结合壁面沸腾模型对管内过冷流动沸腾进行数值模拟,得到了壁面温度、主流温度及空泡份额的分布。基于实验结果对网格模型、湍流模型、壁面沸腾模型及相间作用力模型的参数设置进行了敏感性分析。研究结果表明,对于欧拉双流体模型,并非网格量越多结果越准确,加热面第1层网格的高度对结果影响显著。湍流模型和曳力模型对计算结果影响较小,非曳力中的湍流耗散力及升力对结果影响较大。Li Quan或Hibiki Ishii汽化核心密度模型与Kocamustafaogullari气泡脱离直径模型组合对壁面温度及空泡份额的计算较准确。本研究可为反应堆燃料组件内过冷流动沸腾数值模拟提供参考依据。     

钠冷快堆六角形组件换热特性分析

钠冷快堆乏燃料组件在转运过程中,会暴露在传热性能较差的氩气环境中。为保证燃料组件温度在转运过程中低于安全限值,本研究基于37棒燃料组件开展了在氩气环境下的实验研究及数值模拟计算。研究结果表明：可采用等效导热法对组件内绕丝模型进行简化,简化模型能满足计算精度要求。将计算结果与实验研究结果进行对比分析,结果表明数值模拟方法能较好模拟组件在氩气环境下的换热。六角形燃料组件在氩气中的换热分析中,辐射换热具有重要的影响,实验工况下辐射换热占总换热量的36%～57%。