安全壳模型装置内氢气分布特性及影响因素分析

采用计算流体力学方法,首先利用THAI HM-2实验对CFX分析模型的适用性进行验证,通过与实验数据的比对,表明计算结果与实验数据基本吻合,从而验证选用的模型适合对安全壳模拟装置氢气分布特性的分析。之后,建立待研究中等规模安全壳模型实验装置的三维几何模型和网格模型,采用基准工况+单因素对比的方式,分别模拟湍流浮力射流中心喷射和近壁面喷射工况以及考虑蒸汽壁面冷凝情况下安全壳模型内的氦气(氢气替代工质)流动扩散分布,讨论喷射位置因素、壁面蒸汽凝结效应对氦气分布的影响。分析结果表明,喷射位置对氦气分布的影响主要体现在壁面引流现象上,即氦气流更倾向于沿着安全壳壁面进行流动和扩散;而与安全壳壁面的换热和蒸汽的冷凝会进一步促进大空间自然对流的建立,从而较为显著地提高氦气在安全壳内的扩散和混合效果。     

10 mm垂直单管通道内超临界水传热弱化现象的实验与数值分析

超临界压力下的流体因拟临界点附近物性的剧烈变化,形成了非常奇特的传热现象。因流体密度突变,在低流量下会引起强烈的浮升力作用,对超临界流体的流动和传热均有极大影响。本工作通过实验获得10 mm单管内传热弱化现象的实验数据,并采用改进的低雷诺数湍流模型,使用数值方法模拟该传热弱化现象。计算结果表明,不同于以往传统的模型会高估壁面温度,改进的低雷诺数湍流模型能较好预测实验结果。数值模拟结果还揭示了浮升力对湍流剪切应力和速度分布的影响,进而引起传热弱化和传热恢复。     

超临界压力CO2在垂直管内对流换热数值模拟

对于超临界压力CO2在垂直圆管(din=2 mm)内高进口雷诺数(Re=9 000)条件下向上流动时的对流换热进行了数值模拟.通过与实验数据进行对比来验证湍流模型的可靠性,并研究变物性和浮升力对壁面温度和湍动能的影响.结果表明:在热流密度较高的情况下,向上流动时出现了局部换热恶化和换热强化现象,这主要归因于浮升力对湍动能分布的影响;采用LB湍流模型能较好地模拟这种换热现象;在热流密度较低的情况下,未出现上述换热现象.     

竖直圆管内跨临界压力区水对流传热数值模拟研究

应用CFD方法对跨临界压力区竖直圆管内水的对流传热进行了数值模拟研究。通过与实验结果比较，分析了浮升力因素的影响机理。研究结果表明，采用浮升力修正的k-ε两方程湍流模型可准确预测跨临界压力区正常对流传热现象。当流体温度达到拟临界点，尽管该模型可预测传热恶化现象，但与实验数据偏差较大，在水热物性及数值模型等方面有待进行更深入研究。     

严重事故下安全壳内氢气浓度场分布

利用计算流体力学程序FLuENT和GASFLOW,采用不同的湍流模型,研究了核电站严重事故下氢气在安全壳内的传输与混合过程.计算结果表明,FLUENT中的RNG k-ε模型能够较好的模拟氢气的质量扩散,动量扩散和湍流脉动特征;FLUENT中的标准k-ε模型和GASFLOW中的k-ε模型能得到工程上可以接受的计算结果;而GASFLOW中代数模型未能较好地模拟氢气的质量扩散和动量扩散,氢气的浓度场分布与其他模型的计算结果存在较大的差别.同时,本文对混合气体中的水蒸汽浓度和气体的质量流速对安全壳内氢气浓度分布的影响进行了初步研究.研究表明,破口气体的密度和流速是影响氢气浓度场的重要因素;混合气体密度越小、流速越大,则有更大的浮力和初始动量作用于气体.湍流模型的选择和对浮力驱动的湍流射流的模拟是影响严重事故下氢气在安全壳内的分布模拟结果的重要因素.     

严重事故下安全壳内氢气浓度场分布影响因素的初步研究

利用计算流体力学程序FLUENT和GASFLOW，采用不同的湍流模型，研究了核电站严重事故下氢气在安全壳内的传输与混合过程。计算结果表明，FLUENT中的RNGk-ε模型能够较好的模拟氢气的质量扩散，动量扩散和湍流脉动特征；FLUENT中的标准k-ε模型和GASFLOW中的k-ε模型能得到工程上可以接受的计算结果；而GASFLOW中代数模型未能较好地模拟氢气的质量扩散和动量扩散，氢气的浓度场分布与其他模型的计算结果存在较大的差别。同时，本文对混合气体中的水蒸汽浓度和气体的质量流速对安全壳内氢气浓度分布的影响进行了初步研究。研究表明，破口气体的密度和流速是影响氢气浓度场的重要因素；混合气体密度越小、流速越大，则有更大的浮力和初始动量作用于气体。湍流模型的选择和对浮力驱动的湍流射流的模拟是影响严重事故下氢气在安全壳内的分布模拟结果的重要因素。     

强浮升力作用下超临界流体对流换热的湍流模型研究

针对湍流模型中浮升力相关项的模型进行了比较分析,在此基础上进行了一系列修正;最后,分别使用修正的模型和传统模型计算了超临界压力下的对流传热,并将计算结果与实验数据进行了比较.结果表明,修正的湍流模型能比较准确地模拟浮升力项,从而使计算得到的壁温与实验数据、DNS数据符合较好;而传统模型计算得到的壁温比实验数据、DNS数...     

安全壳大空间内氢气分层行为的模型研究

基于蒸汽/氢气混合喷放下安全壳大空间内氢气分层行为的主导机制——惯性力、粘性力及浮升力间的相互作用,通过理论建模与实验拟合的方法,得到了预测氢气分布特性的半经验关系式,通过与环境中喷入中等蒸汽浓度及高蒸汽浓度实验数据的比较,验证了该模型的合理性,可为后期耦合安全壳内蒸汽冷凝行为影响下的氢气分布理论模型的开发提供辅助支撑;同时,通过将其应用于CAP1400缩比安全壳模型中典型氢气行为的研究发现,在容器轴向位置可能形成轻质气体积聚区、浓度梯度区及滞止区,该结果与国际基准实验（ISP47）的相关发现一致。      

严重事故下安全壳内氢气爆燃风险数值模拟研究

采用计算流体力学(CFD)方法对典型核电厂失水事故下的氢气分布和燃烧过程进行安全分析研究。首先基于火焰加速准则对安全壳内燃爆风险进行评估,采用大规模氢气燃烧实验确定了保守燃烧模型(CREBCOM)中的燃烧速率常数。对安全壳内的氢气燃烧过程的数值模拟显示:氢气燃烧过程产生的峰值压力接近7.0×10~5 Pa,将对安全壳完整性产生威胁。     

垂直矩形通道内的混合对流实验与数值研究

对耦合了热辐射的垂直矩形通道内的混合对流情况进行了实验研究和数值模拟分析.研究表明:空气在通道内向上流动时,随着浮升力作用的增大,对流换热能力表现出先减小后增强的趋势;热辐射在换热过程中起着重要的作用,并随着对流换热能力的减弱而增强.数值模拟在浮升力影响较小时可以给出较好的结果,当浮升力影响比较大时,数值模拟计算的结果与实验有较大的偏差.     

Experimental investigation of spray induced gas stratification break-up and mixing in two interconnected vessels

To analyze the effect of containment spray on gas mixing and depressurization, two experiments (ST3_1 and ST3_2) were performed with two interconnected vessels. These experiments were conducted in the frame of the OECD/SETH-2 project using the PANDA facility. The vessels were preconditioned such that a helium-rich layer is formed in the upper section of the first vessel, henceforth referred to as Vessel-1. In the case of the first experiment (ST3_1), the remaining volume of Vessel-1 and the entirety of the second vessel, Vessel-2, were filled with pure steam. For ST3_2, the second experiment presented here, pure steam was replaced with a steam-air mixture instead. Water was injected from the top of Vessel-1 with a spray nozzle projecting downwards. Transient behavior of system pressure, as well as global redistribution of gases is investigated. The results reveal that spray activation is very effective in containment system depressurization. Additionally it is found that the depressurization occurs at a higher rate for the systems containing more steam and less non-condensible gas. The depressurization rate gradually slows down, however, as the steam concentration decreases due to condensation, and non-condensible gases spread over the vessel system. It is also observed that the spray activation initiates the breakup of the helium-rich layer. The composition of the gas atmosphere plays a crucial role in determining the initiation time of the breakup; the presence of large amounts of non-condensible gas such as air delays the beginning of the helium layer breakup by approximately 200 s. The downward component of spray momentum causes the entrainment and the recirculation of the ambient gas atmosphere. Together with the entrainment and condensation effect, spray activation influences the gas mixture density in Vessel-1 and this generates a driving force for inter-compartment flow. As a result of this, an increase of helium-rich gas mixture is observed in the regions far away from the spray, i.e., in Vessel-2.     

不同湍流模型对氢气分布影响的数值研究

研究严重事故下安全壳内氢气分布有利于评估氢气风险。本文采用三维CFD方法对THAI装置HM2试验进行建模,并分别使用代数模型和k-ε模型模拟氢气分层形成以及破坏过程。分析结果表明,CFD模拟结果与实验数据基本符合,在模拟中可观察到氢气分层现象的形成以及水蒸气对氢气分层的逐步破坏与混合过程;在氢气注射阶段,代数模型和k-ε模型的模拟结果接近,能够反映氢气浓度分层的形成过程;在水蒸气注射阶段,代数模型基于半经验的混合长度理论,在模拟装置较复杂几何结构内水蒸气流动对氢气分层的破坏作用时并不十分理想,标准k-ε模型对装置各测点氢气浓度达到一致的时间预测与试验结果较为接近。     

New gas concentration measurement system for the PANDA containment test facility

The increased use of computational fluid dynamics code for analysis and design purposes demands high quality experimental data to validate the simulation codes. Experimental data of fluid stratification and stratification break-up phenomena are generated in the frame of OECD/SETH-2 project at the PANDA facility. A new gas concentration measurement system is presented that is based on speed of sound measurements. Speed of sound in gas mixtures is a unique function of the temperature and the fractions of the components and therefore can be used to compute the fractions in varying compositions. The speed of sound is measured indirectly measuring the time of flight of an ultrasound pulse between two ultrasound transducers. The 30 transducers employed proved to be able to withstand the unfavorable conditions inside the facility with temperatures of up to 110 °C and steam that may condense. A frame rate (1 frame = each transducer has been excited) of 1.6 Hz and a helium fraction resolution of 1.5% in steam are achieved.     

Validation of a Computational Simulation Method for Evaluating Thermal Stratification in the Reactor Vessel Upper Plenum of Fast Reactors

Validation of a numerical simulation method is carried out for thermal stratification phenomena in the reactor vessel upper plenum of advanced sodium-cooled fast reactors. The study mainly focuses on the fundamental applicability of commercial computational fluid dynamics (CFD) codes as well as an inhouse code to the evaluation of thermal stratification behavior including the simulation methods such as spatial mesh distribution and RANS-type turbulence models in the analyses. Two kinds of thermal stratification tests are used in the validation, which is done for relatively simple- and conventional-type upper plenum geometries with water and sodium as working fluids. Quantitative comparison between the simulation and test results clarifies that when used with a high-order discretization scheme of the convection term, the investigated CFD codes are applicable to evaluations of the basic behaviors of thermal stratification and especially the vertical temperature gradient of the stratification interface, which is important from the viewpoint of structural integrity. No remarkable difference is seen in the simulation results obtained using different RANS turbulence models, namely, the standard kε model, the RNG k-ε model, and the Reynolds stress model. It is further confirmed in a numerical experiment that the distribution of two or more meshes within the stratification interface will lead to accurate simulation of the interface temperature gradient with less than 10% error.     

Simulation of containment jet flows including condensation

The validation of a CFD code for light-water reactor containment applications requires among others the presence of steam in the different flow types like jets or buoyant plumes and leads to the need to simulate condensation phenomena.In this context the paper addresses the simulation of two “HYJET” experiments from the former Battelle Model Containment by the CFD code CFX. These experiments involve jet releases into the multi-compartment geometry of the test facility accompanied by condensation of steam at walls and in the bulk gas. In both experiments mixtures of helium and steam are injected. Helium is used to simulate hydrogen. One experiment represents a fast jet whereas in the second test a slow release of helium and steam is investigated. CFX was earlier extended by bulk and wall condensation models and is able to model all relevant phenomena observed during the experiments. The paper focuses on the simulation of the two experiments employing an identical model set-up. This provides together with other validation exercises the information on how well a wider range of flowing conditions in a full containment simulation can be covered with a single set of models (e.g. turbulence and condensation model). Some aspects related to numerical and modelling uncertainties of CFD calculations are included in the paper by investigating different turbulence models together with the modelling errors of the differencing schemes applied.     

OECD International Standard Problem ISP-47 on containment thermal-hydraulics—Conclusions of the TOSQAN part

The main objective of the ISP-47 is to assess the capabilities of Lumped-Parameter and Computational Fluid Dynamics codes in the area of nuclear containment thermal-hydraulics. Three experimental facilities TOSQAN, MISTRA and ThAI were involved in this project. The present paper summarizes the specifications, the results and the conclusions obtained for the TOSQAN open benchmark exercise.Wall condensation, steam injection in air or air/helium atmospheres, and buoyancy were addressed under well-controlled initial conditions in the simple TOSQAN geometry. Detailed gas velocity and gas concentration (air, steam and helium) fields were obtained for the first time in such an exercise.It is found that the model predictions fit with a generally good accuracy the experimental results obtained during condensation steady-state conditions, but the flow conditions in the transition regime are not well reproduced by the calculations: some of the major transient phenomena are not always correctly modelled and if so, the transient evolutions or the levels of the concerned variables are not the same in the calculations and in the experiment. Furthermore, two kinds of measurements were specific for TOSQAN: boundary layer measurements and turbulence variables, which were addressed for the first time in such an exercise. It is concluded that more sophisticated modelling in CFD codes for the boundary layers should be developed and that turbulence variables should be addressed more intensively in further exercises.     

Numerical investigation of radial mixing capabilities in strongly buoyancy-influenced vertical, turbulent channel flows

The flow behavior in the HDR downcomer during setting of the initial conditions for blowdown tests is investigated with the numerical simulation program for turbulent channel flows, TURBIT-3. This computer code is based on the complete 3-dimensional non-stationary basic equations for mass, momentum and heat. The subgrid scale models used for the turbulence structures not directly resolved by the grid are extended to take into account the buoyancy in the case of turbulent channel flow. The extended computer code is used to investigate how fast differences in temperature can be reduced, which are caused by inadequate mixing in the lower plenum during upward flow in the downcomer under conditions of mixed convection. It appears that, contrary to the computations neglecting the influences of buoyancy, the temperature differences are rapidly reduced already in the entrance zone of the downcomer. In this zone, local recirculation takes place in the cold region, which is quickly suppressed with increasing distance from the entrance by the intensification of the turbulence effects. A hot chimney extending through the whole downcomer cannot develop. Already at half level, the influence of buoyancy can be considered to be negligible in the downcomer which is assumed adiabatic. Under these conditions it should be possible in principle to set the enthalpy stratification by the planned layout of the experiment in the HDR-pressure vessel.     

温度层结下建筑物群周围流场影响的数值模拟研究

采用RNG k-ε湍流模型模拟温度层结下建筑物群对流场结构的影响,并用风洞实验结果对模拟结果进行验证分析。结果表明:CFD 模拟结果与Yassin风洞实验结果能较好地吻合,稳定层结建筑尾流区范围内速度和湍流动能减小。通过对稳定、中性和不稳定条件下模拟结果的比较分析,确定了温度层结对规则建筑物矩阵中流动的影响。同时,温度层结对矩阵中街谷涡旋强度和纵向速度垂直分布有着显著影响,特别是当大气处于稳定条件时,建筑物对速度的衰减作用较为明显。     

Numerical Investigation of Channel for Helium Cooled China HCCB-TBM First Wall by Application Enhance Heat Transfer Method

To enhance heat transfer efficiency on first wall (FW) of ITER China Helium-Cooled Ceramic Breeder-Test Blanket Module (HCCB-TBM), CFD numerical simulation method is adopted. On the basis of calculating helium gas cooling scheme of FW smooth channel, FW structural temperature gradient, maximum wall temperature, average heat transfer coefficient, and pressure drop of channel are selected as evaluation indexes. Numerical simulation comparison are performed on heat transfer schemes like placing transversal ribs and V-shaped ribs in the flow channel of front wall and the helium gas turbulence intensity and the heat transfer area are improved through optimizing the distance and angle between V-shaped ribs and other parameters to enhance heat transfer. The optimization scheme of helium-cooled FW for HCCB-TBM through the three dimensional numerical simulation is: V-shaped ribs are placed on the inner surface of front wall, the rib cross section is 1 mm × 1 mm, the distance between rib pitches is 10 mm and the rib angle is 60°. Under the same helium cooling condition, compared with the FW smooth channel, the optimized V-shaped rib scheme enhances the average heat transfer efficiency by about 70 % and the FW maximum temperature drops by 349.3 K. The result provides support for further research on FW helium cooling heat transfer enhancement experiment and engineering design optimization for China HCCB-TBM.