蒸汽发生器内二次侧水位对倒U型管内倒流特性的影响分析

在自然循环条件下,蒸汽发生器(SG)倒U型管内的流体流动会不稳定,可造成一部分倒U型管内流体处于倒流状态。基于Boussinesq假设,建立了与SG二次侧水位有关的倒U型管内流体一维守恒控制方程,采用线性微扰理论分析SG二次侧水位对倒U型管内倒流特性的影响,并采用RELAP5/MOD3.2程序进行了数值模拟。结果表明:在一定倒U型管进口条件下,SG二次侧水位的降低使倒U型管内流动的特征压降增大,特征流量减少,稳定性参数增加,相对于正常水位时更易不稳定,倒流更易发生,长管较短管更易发生倒流。     

直流蒸汽发生器动态特性与小破口故障仿真研究

以B&W直流蒸汽发生器为对象,基于过程仿真软件（APROS）支撑平台中的基本模块,建立了图形化的直流蒸汽发生器仿真模型。对模型进行变工况下的稳态和动态仿真,由结果可知,一次侧入口焓值与二次侧出口压力对稳态特性影响最大,一次侧入口温度对动态特性影响最大。进一步研究直流蒸汽发生器发生换热管破裂事故时,破口位置和破裂程度对其运行特性的影响。结果表明,破口发生位置接近一次侧入口时,对直流蒸汽发生器运行影响最大;换热管破裂对直流蒸汽发生器运行特性的影响随着破裂程度的增加而增大。      

不同运行工况下蒸汽发生器热工水力稳态特性数值研究

基于相似模化理论建立了蒸汽发生器一、二回路流体及传热管流 固耦合传热的单元管三维物理模型,对大亚湾核电厂蒸汽发生器不同工况下的热工水力稳态特性进行了数值模拟研究。采用热相变模型描述二回路汽液两相流动与换热、流-固耦合模型描述一回路冷却剂借助U型管与二回路流体换热。数值计算结果表明：满负荷运行时,传热管内壁温度变化趋势与一次侧流体基本一致,外壁温度与二次侧流体温度变化趋势相同;截面平均含汽率沿传热管高度的升高呈上升趋势,出口质量含汽率与大亚湾核电厂实际运行参数相符;随负荷降低一回路出口温度基本不变,二回路出口温度升高,质量含汽率及传热系数下降,平均传热系数与Rohsenow经验关联式的计算结果基本吻合。     

自然循环条件下倒U型管蒸汽发生器一次侧倒流现象关键影响因素研究

倒U型管蒸汽发生器（UTSG）在自然循环条件下存在倒流现象，影响一回路冷却剂系统载热能力及自然循环能力。本文参照芬兰压水堆热工实验装置（PWR PACTEL）中UTSG设计参数，利用计算流体力学（CFD）软件Fluent模拟流量匀速下降工况下UTSG中的倒流现象，研究一次侧运行参数、UTSG设计参数以及二次侧运行参数对于倒流现象的影响。结果表明，提高UTSG一次侧温度、一次侧运行压力、倒U型管热导率将增大UTSG的临界质量流量，使得UTSG更易发生倒流；提高UTSG二次侧给水量、二次侧温度以及倒U型管内壁粗糙度将使得UTSG临界质量流量下降，抑制倒流现象发生；而倒U型管壁厚对倒流现象几乎无影响；相较于改变二回路温度，改变一回路温度对于倒流现象的影响更为显著。本研究结果可为UTSG的参数优化提供一定参考。      

Analysis of Reverse Flow in Inverted U-Tubes of Steam Generator under Natural Circulation Condition

In this paper, we report on the analysis of reverse flow in inverted U-tubes of a steam generator under natural circulation condition. The mechanism of reverse flow in inverted U-tubes of the steam generator with natural circulation is graphically analyzed by using the full-range characteristic curve of parallel U-tubes. The mathematical model and numerical calculation method for analyzing the reverse flow in inverted U-tubes of the steam generator with natural circulation have been developed. The reverse flow in an inverted U-tube steam generator of a simulated pressurized water reactor with natural circulation is analyzed. Through the calculation, the mass flow rates of normal and reverse flows in individual U-tubes are obtained. The predicted sharp drop of the fluid temperature in the inlet plenum of the steam generator due to reverse flow agrees very well with the experimental data. This indicates that the developed mathematical model and solution method can be used to correctly predict the reverse flow in the inverted U-tubes of the steam generator with natural circulation. The obtained results also show that in the analysis of natural circulation flow in the primary circuit, the reverse flow in the inverted U-tubes of the steam generator must be taken into account.     

海洋核动力平台一回路摇摆状态下自然循环能力研究

针对海洋核动力平台的结构和运行特点,建立了一回路流量瞬态分析计算模型,开发了海洋核动力平台自然循环计算程序。该程序可计算核动力平台横向摇摆对自然循环的影响。计算结果显示,摇摆状态将对自然循环产生不利影响,45°横向摇摆将使自然循环流量下降约5%,对于一回路的布置,提高蒸汽发生器的设备高度和减小泵的阻力系数能有效降低自然循环状态下堆芯温度和提高自然循环流量。     

Heat transfer characteristics of horizontal steam generators under natural circulation conditions

This paper deals with the heat transfer characteristics of horizontal steam generators, particularly under natural circulation (decay heat removal) conditions on the primary side. Special emphasis is on the inherent features of horizontal steam generator behaviour. A mathematical model of the horizontal steam generator primary side is developed and qualitative results are obtained analytically. A computer code, called HSG, is developed to solve the model numerically, and its predictions are compared with experimental data. The code is employed to obtain for VVER 440 steam generators quantitative results concerning the dependence of primary-to-secondary heat transfer efficiency on the primary side flow rate, temperature and secondary level. It turns out that the depletion of the secondary inventory leads to an inherent limitation of the decay energy removal in VVER steam generators. The limitation arises as a consequence of the steam generator tube bundle geometry. As an example, it is shown that the grace period associated with pressurizer safety valve opening during a station black-out is hours instead of the 5–6 hours reported in several earlier studies. (However, the change in core heat-up timing is much less—about 1 h at most.) The heat transfer limitation explains the fact that, in the Greifswald VVER 440 station black-out accident in 1975, the steam generators never boiled dry. In addition, the stability of single-phase natural circulation is discussed and insights on the modelling of horizontal steam generators with general-purpose thermal-hydraulic system codes are also presented.     

倒U型管蒸汽发生器自然循环回流特性研究

自然循环在核动力工业中有重要的应用。以AP1000自然循环压水反应堆一回路系统的蒸汽发生器为对象,建立自然循环系统蒸汽发生器倒U型管内单相水回流的数学模型,并进行了计算,得出了蒸汽发生器倒U型管内正流和回流流量、正流管管长和回流管管长分布等。研究结果表明,回流能大幅降低自然循环的重位压头、流量和放热量,不利于自然循环。     

基于漂移流模型的蒸汽发生器稳态热工水力分析

为研究蒸汽发生器的稳态热工水力特性,建立了四方程漂移流模型,并开发了一维计算程序。对蒸汽发生器U型管管束空间考虑为由一次侧通道、二次侧通道和传热管构成,对一次侧通道和二次侧通道的过冷段采用单相流模型,二次侧通道的沸腾段采用四方程漂移流模型,建立基于交错网格的一阶迎风差分方程,通过热平衡-自然循环压降的交叉迭代计算得到稳态热工水力参数。利用程序计算了秦山300 MW核电厂100%、75%、50%、30%、15%功率稳定运行工况下的热工水力特性,并与RELAP5的计算结果进行比较,两组结果一致性较好。     

HTR-10蒸汽发生器的建模及分析

为开发适用于球床模块式高温气冷堆HTR-10的模拟机,采用一体化仿真支撑平台vPower建立了蒸汽发生器的实时热工水力模型。模型以传热方程为基础求解两侧工质及金属管壁的温度和焓,以流体网络为基础求解两侧工质的压力和流量。本文讨论了3种节点划分方案,针对不同节点划分方案的适用范围提出了建议并采用96节点划分方案进行后续研究。此外,通过分析确认了模型在稳态工况下主要参数和分布参数的准确性和合理性,并在100%功率稳态工况的基础上模拟了氦气侧流量阶跃的场景,分析了模型中主要参数的变化过程。动态仿真结果表明,氦气流量阶跃会引起一、二次侧参数不同程度的变化,变化幅度与阶跃程度呈正比,且金属管壁和水侧热容、二次侧参数变化速率相对缓慢,模型再平衡时间较短,表明HTR-10采用的螺旋管式直流蒸汽发生器的热惯性相对较小。     

基于CFD的蒸汽发生器U型管内回流现象数值分析

反应堆一回路系统在自然循环条件下，蒸汽发生器（SG）部分U型管内可能会出现回流现象，利用计算流体动力学（CFD）方法，对某非能动三代反应堆蒸汽发生器U型管内流体的流动传热特性进行数值模拟分析。选取6组不同管长的U型管，对比分析U型管内单相流体的流动传热特性。基于数值仿真结果，得出6组U型管质量流量-进出口压降曲线，并?T分析了U型管长度和一次侧进口流体温度与二次侧壁面温度温差（?T）对流体回流的影响。研究结果表明，当?T一定时，随着进出口压降的降低，长管内更容易发生回流。当U型管长度一定时，?T越小越容易发生回流。      

非能动余热排出系统敏感性分析

以中国改进型压水堆核电站CPR1000为研究对象,在其蒸汽发生器二次侧设计了一套非能动余热排出系统（PRHRS）,该系统采用在蒸汽发生器二次侧建立自然循环的方式间接带走堆芯余热,确保事故条件下堆芯安全。用RELAP5/MOD3.2程序对系统进行了合理的简化并建模,在全场断电（SBO）事故条件下模拟了PRHRS的瞬态响应过程,并对高位水箱的容积、PRHRS换热器的换热面积、冷热中心高度差以及PRHRS的投入时间等影响PRHRS工作特性的相关参数进行了敏感性分析。计算结果表明：增加高位水箱的容积和增大换热面积均有助于二次侧余热排出系统带走一回路的堆芯余热;降低冷热中心高度差对PRHRS的自然循环能力影响不大;余热排出系统投入时间越早,蒸汽发生器二次侧水位越高,越有利于一次侧余热的排出。     

自然循环蒸汽发生器并联倒U型管流量分配计算

针对自然循环工况下蒸汽发生器部分倒U型管内存在倒流现象,通过对倒U型管内流动传热特性进行分析,获得了倒流发生的判断依据,从而编制了流量分配计算程序。采用该程序对某型蒸汽发生器并联倒U型管流量分配进行了计算,通过将结果与实验值进行对比分析,对程序可信度进行了验证,并采用该程序对蒸汽发生器并联倒U型管主要热工参数随进出口压降变化情况进行了计算分析。结果表明,倒流现象发生在短管内,倒流的发生使得蒸汽发生器一次侧净流量和单位时间输热呈阶梯下降,对反应堆安全产生较大的影响。     

蒸汽发生器U型管低含气率两相倒流现象研究

针对立式倒U型管自然循环蒸汽发生器传热管内的两相倒流现象，基于均相流模型，建立了U型管内低含气率两相流动传热理论模型，给出了U型管的进出口压降-质量流量曲线，分析了U型管内出现两相倒流现象的机理，研究了二次侧流体温度和入口含气率对倒流现象的影响规律，并与单相倒流进行了对比。利用RELAP5/MOD 3.3程序对相同条件下的倒流问题进行了计算。研究表明，提高蒸汽发生器二次侧工作压力可减少倒流，两相流入口含气率越高，倒流越易发生，两相流较单相流在U型管内更易倒流。     

螺旋管直流蒸汽发生器一、二次侧耦合传热特性分析

To study the flow and heat transfer characteristics of the primary and secondary sides of the helical coil once-through tube steam generator (HCOTSG) under steady state conditions, taking HCOTSG of International Reactor Innovative and Secure (IRIS) as the research object, a primary and secondary sides heat balance calculation model for steady state operation of HCOTSG is established. The influence of different secondary side feed water flow rate on HCOTSG thermal and hydraulic parameters under steady-state condition is analyzed, and the detailed thermal and hydraulic parameters in the helical tube under steady-state condition are calculated by combining the coupled thermal analysis model with the three-dimensional flow and heat exchange calculation of CFX. The relevant thermal and hydraulic parameters along the tube side of HCOTSG during steady-state operation are calculated by the thermal analysis model. The CFX simulation results show that the velocity and temperature distribution of the fluid in the cross section of the helical tube are not uniform. The temperature of the fluid inside the helix is higher than that outside the helix. The velocity of the fluid inside the helix is lower than that outside the helix. The boiling of the fluid inside the helix occurs earlier than that outside the helix. Therefore, this study has a guiding role in the accident analysis for HCOTSG steady-state operation and spiral heat exchange tube.     

螺旋管直流蒸汽发生器一、二次侧耦合传热特性分析

为获得螺旋管直流蒸汽发生器（HCOTSG）螺旋换热管内两相流动换热特征，以国际革新安全反应堆（IRIS）HCOTSG为研究对象建立了HCOTSG一、二次侧耦合热分析模型，分析了稳态工况下，不同二次侧给水流量对HCOTSG热工水力参数产生的影响，并将所建立的HCOTSG一、二次侧耦合热分析模型与计算流体力学软件（CFX）三维流动换热计算相结合，对HCOTSG稳态工况下螺旋管内精细的热工水力参数进行计算。通过HCOTSG一、二次侧耦合热分析模型计算得到HCOTSG稳态工作时沿管程的相关热工水力参数；通过CFX三维模拟发现螺旋管横截面流体流速和温度分布不均匀现象，得到螺旋内侧流体温度高于螺旋外侧，螺旋内侧流体速度低于螺旋外侧，螺旋内侧流体比螺旋外侧流体先开始沸腾的结论。因此，本研究对于HCOTSG稳态运行和螺旋换热管事故分析具有指导作用。      

运行条件对蒸汽发生器热工参数影响的仿真研究

以减轻蒸汽发生器破管事故及考察核电站电力升级为目的,参考大亚湾核电站蒸汽发生器的运行参数,基于分布参数法建立了核动力蒸汽发生器一维数学模型,开发了基于MATLAB的动态仿真程序,进行了改变运行条件时蒸汽发生器热工参数仿真计算。计算结果表明:与满负荷正常运行条件相比,在降低二回路运行温度或增加二回路流量时,二回路预热段变短,出口焓大幅升高;质量含汽率在降低温度时提高54%,增加流量时提高28%;一、二回路及管壁整体温度降低;一回路和内壁温降增大。该计算结果揭示了蒸汽发生器的内在传热规律,可为缓解U形管恶化及提升电力的相关操作提供一定理论依据。     

基于多孔介质模型的快堆蒸汽发生器热工水力特性数值研究

蒸汽发生器（SG）作为钠冷快堆一次侧钠与二次侧水的热交换器，其可靠程度直接影响反应堆能否安全运行，因此对SG的一次侧热工水力特性的研究具有重要意义。本研究采用多孔介质模型，对快堆蒸汽发生器一次侧流场进行分析。通过对支撑板模型的计算，获得多孔介质控制方程的阻力源项。一次侧向二次侧的释热量通过系统程序Relap5计算，确定多孔介质控制方程的能量源项。通过用户自定义程序将动量源项与能量源项编译至FLUENT求解器中。通过FLUENT求解器求解控制方程，获得SG一次侧流场、压力场、温度场等信息。并通过对比模拟结果与设计值，验证了计算的准确性。      

A theoretical model for the calculation of large transients in nuclear natural-circulation U-tube steam generators (Digital code UTSG)

A newly developed nonlinear transient model for the calculation of the dynamic behaviour of a vertical natural-circulation U-tube steam generator together with its steam removal system is presented. The steam generator is considered to consist of a heat exchange section, a top plenum, a downcomer region and a steam removal system with a sequence of relief and/or safety valves, isolation, bypass, turbine-trip and turbine-control valves and a steam turbine. Possible perturbations from outside can be: inlet water temperature, inlet water mass flow and system pressure on the primary side, feed water temperature, feed water mass flow and outlet steam mass flow disturbed by actions of the different valves within the steam removal system on the secondary side. Based on this theoretical model the digital code UTSG has been established. Post-calculations of start-up tests at a PWR nuclear power plant simulating perturbations both on the primary and secondary side of the steam generator and similar calculations for the corresponding ATWS-cases will show the efficiency of the code UTSG and the underlying theoretical model.     

Non-dimensional analysis of static bifurcation in a natural circulation loop

The steady-state characteristics of a two-phase natural circulation loop were investigated based on the homogenous model. Transcendental equations of non-dimensional loop mass flow rate under various conditions were also derived. The static bifurcation diagram of a two-phase natural circulation described with non-dimensional variables Npch-m^＋ was obtained. In addition, various steady-state characteristics of a natural circulation loop were analyzed and discussed. These characteristics include the existence of multiple solutions under certain conditions, and the maximum mass flow rate. The authors also examined the effects of important parameters such as sub-cooling number, riser-to-heated-region length ratio, and riser-to-heated-region diameter ratio.