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。      

IVR-ERVC下压水堆压力容器下封头传热及应力/应变分析

以某1000?MW压水堆为例,利用二维极坐标热模型分析RPV壁面与双层堆芯熔池和外部冷却水堆腔之间的传热,计算下封头壁面瞬态二维温度场分布和烧蚀情况,同时通过有限元分析程序计算下封头壁面的各瞬态温度场和烧蚀引起的热应力/应变情况,分析压水堆RPV下封头在压力容器内熔融物滞留-压力容器外冷却（IVR-ERVC）下的结构完整性。计算结果表明:①芯熔融坍塌后200?s下封头壁面开始熔融,最薄厚度直线下降;3000?s后熔融区沿下封头内壁呈一片柳叶形状分布;②下封头内表面的吸热热流大于外表面的散热热流,在两层熔池界面处内外表面热流密度达到最大值;③RPV下封头热应力在0~400?s时集中于下封头内壁面;在400 s后,下封头内壁面热应力逐渐减小,形变量逐渐增大,下封头完整性可以得到保证;④2000?s以后,RPV下封头烧蚀损伤处内外壁面均产生应力集中,下封头烧蚀处内外壁应力值均大于许用应力,在2000?s后有可能发生断裂,在烧蚀损伤边缘处可能出现破口。      

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.     

堵流条件下矩形并联通道非均匀流动传热模拟方法研究

为建立矩形并联通道非均匀流动传热模拟方法,针对板型燃料元件的安全分析提供新的模拟方法和工具,本研究采用一维两流体模型和燃料元件二维导热模型开发热工水力瞬态分析程序,对堵流条件下非均匀流动传热进行模拟。通过数值模拟得到不同堵流工况下流量分配和燃料温度分布,此外对4种不同功率分布下燃料元件二维导热效应进行研究。研究结果表明,堵流后并联通道流量和传热量将重新分配,二维导热模型使燃料元件截面温度场分布更均匀。本文开发的热工水力瞬态分析程序能够用于板型燃料元件非均匀流动传热现象的模拟。     

海洋条件下反应堆热工水力参数的子通道计算

针对海洋条件下反应堆的子通道热工水力分析,建立了海洋运动附加力模型和瞬态入口边界,将起伏、摇摆及复合运动的附加力关系式用于子通道模型的轴向和横向动量方程,并应用到COBRAⅢC程序将其改造为适应海洋条件的反应堆子通道分析程序。作为验证,计算了加热实验通道和"奥陆"堆在起伏运动情况下热通道的临界热流密度比(CHFR)、出口空泡份额和冷却剂流量,并与文献结果对比。还详细计算了"奥陆"堆在起伏、不同摇摆中心和复合运动情况下,热通道的CHFR和不同位置子通道出口的热工水力参数。研究表明:海洋条件下反应堆的子通道热工水力参数随运动呈周期性变化;起伏运动对子通道的压降影响较大,摇摆运动对子通道冷却剂的流量和温度影响较大。     

Steady thermal hydraulic characteristics of nuclear steam generators based on the drift flux code model

To investigate the steady thermal hydraulic characteristics of U-tube steam generator(SG), a 1D simulation code based on the four-equation drift flux model is developed. The U-tube channels presumably consist mainly of the primary channel, secondary channel, and tube wall. In the sub-cooling regions of the primary and secondary channels, flow is simulated using the single-phase flow model, whereas that in the boiling regions of the secondary channels is simulated using the four-equation drift flux model. The first-order equations of upwind difference are derived based on the staggered grid. Steady-state thermal hydraulic parameters are obtained with a cross-iteration scheme of heat balance and natural circulation requirement. The developed code is applied to analyze the SG behavior of the Qinshan I Nuclear Power Plant under 100%, 75%, 50%, 30%, and 15% power conditions. Analysis results are then compared with the simulation results obtained using RELAP5.     

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。