采用非能动余热排出系统实验数据对RELAP5程序的评价

利用非能动余热排出系统1∶10原理性实验台架的稳态实验与启动实验数据,对RELAP5/MOD3.2程序进行评估。结果表明：对于本原理性实验系统,RELAP5/MOD3.2程序过低估算了蒸汽流速对蒸汽凝结换热系数的影响,因而,程序中垂直管内的蒸汽凝结换热系数偏小,计算结果与实验结果偏差大。对RELAP5/MOD3.2程序垂直管内蒸汽凝结换热模型进行了修正,修正后的计算结果与实验值基本吻合。评价结果表明：采用RELAP5/MOD3.2程序对该类型的非能动余热排出系统进行计算,需对程序中垂直管内的蒸汽凝结换热模型进行修正。     

Experimental and numerical investigations on the reverse flow phenomena in UTSGs

Aiming at the reverse flow phenomena in the inverted U-tube steam generators (UTSGs), the experimental and numerical simulations are performed. A new method is developed to model the flow and heat transfer in the steam generator based on the system analysis code RELAP5/MOD3.3. The reverse flow phenomenon observed experimentally is simulated well by the new method. The experimental and numerical results show that the reverse flow occurs in the adjacent shorter U-tubes. For single U-tube, the mass flow rate of reverse flow is generally greater than that of normal flow U-tube. When the reverse flow occurs, the negative pressure drop between the inlet and outlet plenums and the heat transfer of the UTSG reduce significantly. The numerical simulations also show that the reverse flow occurs more easily in UTSGs with the bigger tube length ratio.     

非能动余热排出系统数学模型研究与运行特性分析

利用某型核动力装置非能动余热排出系统1:10原理性试验的8个稳态工况、6个启动工况的试验数据,验证RELAP5/MOD3.2程序对本类型非能动余热排出系统的适用性。结果表明:垂直管内蒸汽凝结换热系数对两相流自然循环的流动与传热影响大;RELAP5/MOD3.2程序过低估算了垂直管内蒸汽流速对蒸汽凝结换热系数的影响,计算结果与试验结果偏差大。对RELAP5/MOD3.2程序垂直管内的蒸汽凝结换热模型进行修正,修正后的计算结果与试验值基本吻合;采用RELAP5程序对垂直管内两相流自然循环传热进行计算,须选择热前沿跟踪模型。对非能动余热排出系统的稳态与瞬态运行特性进行分析,理论计算与试验结果均表明:稳态工况下,系统可以实现稳定的两相流自然循环,系统排热能力受蒸汽发生器水位的影响大,冷却水入口温度与系统压力的影响相对较小;系统的启动特性良好,可快速地建立环路的自然循环,带走反应堆的衰变热。     

An assessment of PWR steam generator condensation at the Oregon State University APEX facility

This report describes the testing to assess steam generator U-tube steam condensation conducted at the Oregon State University Advanced Plant Experiment Test Facility from 2005 to 2007. Six separate SG condensation (without non-condensable gas) tests were conducted as part of this test program. These tests were designed to evaluate steam condensation rates in a scaled Pressurized Water Reactor steam generator at various primary and secondary side pressures and inlet steam mass flow rates. The experimental data will provide a basis to assess TRACE steam generator modeling techniques and to assist in development of improved models for condensation and steam generator thermal-hydraulics.     

水平管内蒸汽冷凝局部换热特性实验研究

以水蒸气为工质,实验研究了水平管内纯蒸汽冷凝的局部换热特性。实验选取换热管内径为25 mm、换热管进口压力为0.15~0.4 MPa、局部蒸汽的Re=5756~92289,分析了蒸汽压力及流速、壁面过冷度对冷凝传热系数的影响,并将采用现有关系式计算的冷凝传热系数与实验结果进行了对比。结果表明：冷凝传热系数随壁面过冷度的增大而减小,随压力的升高和流速的增大而增大;采用现有关系式计算的冷凝传热系数与实验值的偏差较大,关系式有待进一步改进;在实验范围内,由拟合换热关系式计算所得冷凝传热系数与实验结果的相对偏差在15%左右。     

Direct-contact condensation heat transfer model in RELAP5/MOD3.2 with/without noncondensable gases for horizontally stratified flow

Direct-contact condensation experiments on atmospheric steam and steam/air mixture on subcooled water flowing co-currently in nearly-horizontal channels are carried out and the local heat transfer coefficients are obtained. Inlet air mass fraction in the mixture is varied by up to 50%. Based on previous and present experimental data, a direct-contact condensation database is constructed. The horizontally stratified condensation model of RELAP5/MOD3.2 overpredicts both co-current and counter-current experimental data. The correlation proposed by Kim predicts the database relatively well compared with that of RELAP5/MOD3.2. In the presence of noncondensable gases, RELAP5/MOD3.2 overpredicts the database with percentage errors of 55.1 and 61.1% for pipe inclination angles of θ=2.1° and θ=5.0°, respectively. The UCB correction factor is modified to consider the effects of noncondensable gases on heat transfer coefficients. When Kim's correlation is substituted with the Dittus–Boelter type correlation in RELAP5/MOD3.2 and a modified correction factor is used, the prediction errors are greatly reduced to 20.7 and 28.8% for inclination angles of θ=2.1° and θ=5.0°, respectively.     

Experimental and empirical study of steam condensation heat transfer with a noncondensable gas in a small-diameter vertical tube

An experimental study was performed to investigate local condensation heat transfer coefficients in the presence of a noncondensable gas inside a vertical tube. The data obtained from pure steam and steam/nitrogen mixture condensation experiments were compared to study the effects of noncondensable nitrogen gas on the annular film condensation phenomena. The condenser tube had a relatively small inner diameter of 13 mm (about 1/2-in.). The experimental results demonstrated that the local heat transfer coefficients increased as the inlet steam flow rate increased and the inlet nitrogen gas mass fraction decreased. The results obtained using pure steam and a steam/nitrogen mixture with a low inlet nitrogen gas mass fraction were similar. Therefore, the effects of noncondensable gas on steam condensation were weak in small-diameter condenser tubes.A new correlation was developed to evaluate the condensation heat transfer coefficient inside a vertical tube with noncondensable gas, irrespective of the condenser tube diameter. The new correlation proposed herein is capable of predicting heat transfer rates for tube diameters between 1/2- and 2-in. because of the unique approach of accounting for the heat transfer enhancement via an interfacial shear stress factor.     

自然循环条件下蒸汽发生器倒U型管流量分配特性研究

以欧洲压水堆热工实验装置（PWR PACTEL）一回路系统蒸汽发生器为研究对象,首先,基于流体一维流动模型的质量、动量和能量守恒方程建立管道进出口压降以及传热与流体流量之间的关系;其次,以遗传算法为基础开发倒U型管蒸汽发生器流量分配计算程序,采用基准实验对程序正确性和可靠性开展验证;最后,利用流量分配程序计算蒸汽发生器倒U型管管组的流量分布情况,研究管高、管长以及一/二次侧换热系数对蒸汽发生器内流量分配的影响。结果表明,所开发流量分配程序计算结果与实验吻合良好;在选定的自然循环工况下,该蒸汽发生器中长管更易发生倒流,且倒流现象呈现分布范围广、单管流量低的特点;倒U型管内正流流速与管长成反比,与管高成正比,倒流流速随着管长的增加保持不变,与管高呈反比关系;传热系数较低时,总流量与传热系数成反比关系,当传热系数高于特定值后部分管内发生倒流,总流量骤降。      

自然循环U型管蒸汽发生器管内倒流受管长影响的理论研究

自然循环U型管蒸汽发生器（UTSG）在一次侧处于自然循环工况下其部分U型管可能会出现倒流现象,这对自然循环带来不利影响。本文通过理论分析UTSG的U型管的水动力学曲线,获得U型管内发生流动不稳定时的临界压降与管长的关系,并利用系统分析程序RELAP5进行数值验证,验证结果表明:当管长增加时,临界压降呈先减后增的趋势,即小型的UTSG的最短U型管先出现倒流,而大型的UTSG最长管先出现倒流。所得结论解释了不同的仿真模拟研究得到的倒流管的分布不同的现象,为UTSG管内倒流及其管空间分布的预测提供理论依据。      

RELAP5/MOD3.2竖直管束外大容积沸腾换热模型适用性分析

以浸没在大容积水箱内的非能动余热排出换热器为研究对象,采用实验数据对RELAP5/MOD3.2程序计算竖直管束外大容积沸腾换热适用性进行校核。在充分考虑大容积水箱内流体沿管束轴向的自然对流以及径向的气液间热量交换基础上,合理建立了沸腾换热回路节点划分模型。将计算结果与实验数据进行对比,发现沸腾换热系数的计算值与实验值最大相对偏差在50%以上,且沸腾换热系数随热流密度变化的趋势明显不同。由此判断,Chen关系式并不适合计算竖直管束外大容积沸腾的情况。通过与已有的大容积沸腾换热计算关系式对比,发现Kutateladze “new”公式或Rohsenow公式计算值与实验值符合较好。     

两相流模型在直流蒸汽发生器热工水力分析中的比较研究

根据组成气液两相流基本场方程数量所反映的流动与传热特性的不同,两相流方程分为三方程、四方程、五方程和六方程模型,结合流动压降模型、传热模型、两相相互作用模型以及流动工质的状态参数和结构材料热物性等辅助关系式,可很好地对蒸汽产生系统进行设计和研究分析。本文分析了不同数量的两相流场方程的特点和局限性,结合直管式直流蒸汽发生器实验装置,分别选取最佳估算程序中4种不同的两相流场方程计算模型进行流动传热计算分析,重点比较了强制流动的单相过冷水被加热至单相过热蒸汽过程中的压力与传热特性,从而给出不同场方程的两相流模型在分析具有较大相变过程中的差异性,验证了RELAP5程序和RETRAN-3D程序计算分析直流蒸汽发生器的能力。结果表明,RELAP5程序的六方程模型更适合模拟直流蒸汽发生器。     

基于RELAP5的螺旋管蒸汽发生器热工水力程序研发与验证

由于较高的换热效率和紧凑的结构设计,螺旋管式直流蒸汽发生器（HCOTSG）在多种模块化小型堆的设计中得到了广泛应用。RELAP5作为广泛应用于反应堆热工水力特性分析的大型系统程序之一,采用的热工水力关系式仅针对直管模型开发,不适用于HCOTSG一次侧和二次侧。本文选用螺旋管及横掠管束的热工水力模型,基于RELAP5程序开发了HCOTSG模块。采用实验数据及程序对比等方式对螺旋管模块的流动和换热模型进行了单独验证,利用开发的RELAP5-HCOTSG程序针对国际革新安全反应堆（IRIS）的蒸汽发生器设计进行了整体的热工水力模拟,与原始RELAP5的计算相比,RELAP5-HCOTSG程序计算得到的热工水力参数与设计值符合良好,确认了本文开发的程序模块在HCOTSG热工水力分析中的适用性。     

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。     

摇摆条件下非能动余热排出系统运行特性的试验与理论研究

在摇摆台架上对摇摆条件下的非能动余热排出系统运行特性进行了试验研究。在RELAP5/MOD3.2程序的基础上,采用漂移流模型替代两流体模型,通过修正混合物动量方程、冷凝传热模型,对程序进行改进,利用改进的RELAP5程序,对摇摆条件下的非能动余热排出系统进行了数值模拟,计算结果与试验结果相吻合,误差在10%以内。改进的冷凝换热关系式可较好地用于含有液滴夹带的冷凝换热计算。在摇摆试验中,凝水温度与蒸汽压力波动很小。     

蒸汽发生器U型管倒流现象的数值模拟和实验研究

针对蒸汽发生器U型管倒流现象展开实验研究。基于实验数据,采用CFD方法对倒流进行模拟。结果表明:蒸汽发生器发生倒流后,进口腔室出现显著的温度分层,倒流现象降低了蒸汽发生器U型管的换热能力;发生倒流后,进出口腔室压降绝对值减小,正流管流速增大,流动阻力增大,倒流降低了系统的自然循环能力。     

Condensation in the presence of noncondensable gases

An experimental investigation to examine the effects of surface orientation on the condensation of steam in the presence of noncondensable gas is reported. An air-steam mixture was directed into a rectangular flow-channel over a condensing aluminum surface that has a painted surface finish. The mixture flow was concurrent in all the tests with condensate flow. In this series of experiments, the orientation of the condensing surface was varied from 0–90° (plate surface was facing downwards at 0°), with a variable air-steam mass fraction of 0–0.87, and a mixture velocity of 1–3 m/s. The heat transfer coefficient was measured in addition to making visual observations of the condensation process. It was found that the heat transfer coefficient varied from 100 to 600 W/m² K with the mass fraction of 0.87-0.24 and the maximum heat transfer coefficient of 6200 W/m² K was measured with mass fraction of 0. By tilting the condensing surface from the horizontal to vertical position, the heat transfer coefficient decreased 15 to 25% depending on the mass fraction. With a higher vapor content the effect of the orientation was smaller. This dependence was attributed to the existence of interfacial structure (droplets and ridges) that promoted heat transfer at small inclination angles, when the angle was increased the interface became smoother and heat transfer rates decreased. Heat transfer rates were also observed to increase with flow velocity, vapor content and pressure. The results are compared with some previously published data and a proposed condensation model that showed reasonable agreement with the data trends.     

蒸汽发生器一维均相流模型及其换热性能

以大亚湾核电站蒸汽发生器为原型,在合理假设基础上,分别以一回路流体、二回路流体及U形管内、外壁为研究对象,建立了蒸汽发生器一维均相流模型。采用Jacobi迭代法编制了基于MATLAB的仿真程序,对蒸汽发生器不同工况下的稳态换热性能进行计算,得出各流程关键参数的变化规律,计算结果与大亚湾核电站实际运行数据相吻合。计算结果揭示了蒸汽发生器的内在传热规律,可为蒸汽发生器优化设计提供一定的理论依据。     

补水箱水装量对非能动余热排出系统运行的影响分析

为了补充非能动余热排出系统运行过程中蒸汽发生器二次侧流体的损失量,设置了补水箱。采用RELAP5程序进行建模分析,评估不同补水箱初始水装量对非能动余热排出系统运行造成的影响。结果表明,设置补水箱有利于建立蒸汽发生器内部长期的稳定运行状态;补水箱初始水装量越高,在补水阶段对非能动余热排出系统的换热能力抑制效应越明显,但补水结束后的长期阶段,由前期补水对非能动余热排出系统运行所造成的影响不大。     

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。     

直流蒸汽发生器传热管破裂事故分析

通过对直流蒸汽发生器传热管破裂（SGTR）事故的分析,可看出RELAP5瞬态分析程序能较好地模拟一体化反应堆在SGTR事故后的事件响应序列及主要热工水力现象,例如环路的不对称效应、主回路的自然循环等。一体化反应堆在发生SGTR事故后,可通过一系列安全与保护系统的动作得到有效缓解,并最终能应用非能动余热排出系统（PRHRS）的自然循环导出堆芯余热,使反应堆处于安全状态。同时,受事故影响蒸汽发生器压力在PRHRS投入运行后会快速升高,最终与一回路压力相平衡,此后,破口处的泄漏也会终止。此外,本文还研究了破口处临界流量及其积分流量结果不确定性的影响因素,其中主要考虑了采用不同的临界流模型和破口建模方式等两个方面。