首页> 外文期刊>Journal of Engineering for Gas Turbines and Power >Air/water Counter-current Flow Experiments In A Model Of The Hot Leg Of A Pressurized Water Reactor
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Air/water Counter-current Flow Experiments In A Model Of The Hot Leg Of A Pressurized Water Reactor

机译:压水堆热腿模型中的空气/水逆流实验

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Different scenarios of small break loss of coolant accident for pressurized water reactors (PWRs) lead to the reflux-condenser mode in which steam enters the hot leg from the reactor pressure vessel (RPV) and condenses in the steam generator. A limitation of the condensate backflow toward the RPV by the steam flowing in counter current could affect the core cooling and must be prevented. The simulation of counter-current flow limitation conditions, which is dominated by 3D effects, requires the use of a computational fluid dynamics (CFD) approach. These numerical methods are not yet mature, so dedicated experimental data are needed for validation purposes. In order to investigate the two-phase flow behavior in a complex reactor-typical geometry and to supply suitable data for CFD code validation, the "hot leg model" was built at Forschungszentrum Dresden-Rossendorf (FZD). This setup is devoted to optical measurement techniques, and therefore, aflat test-section design was chosen with a width of 50 mm. The test section outlines represent the hot leg of a German Konvoi PWR at a scale of 1:3 (i.e., 250 mm channel height). The test section is mounted between two separators, one simulating the RPV and the other is connected to the steam generator inlet chamber. The hot leg model is operated under pressure equilibrium in the pressure vessel of the TOPFLOW facility of FZD. The air/water experiments presented in this article focus on the flow structure observed in the region of the riser and of the steam generator inlet chamber at room temperature and pressures up to 3 bar. The performed high-speed observations show the evolution of the stratified interface and the distribution of the two-phase mixture (droplets and bubbles). The counter-current flow limitation was quantified using the variation in the water levels measured in the separators. A confrontation with the images indicates that the initiation of flooding coincides with the reversal of the flow in the horizontal part of the hot leg. Afterward, bigger waves are generated, which develop to slugs. Furthermore, the flooding points obtained from the experiments were compared with empirical correlations available in literature. A good overall agreement was obtained, while the zero penetration was found at lower values of the gaseous Wallis parameter compared with previous work. This deviation can be attributed to the rectangular cross section of the hot leg model.
机译:压水堆(PWR)的冷却剂意外事故造成的小断裂损失的不同情况导致回流冷凝器模式,其中蒸汽从反应堆压力容器(RPV)进入热段并在蒸汽发生器中冷凝。逆流流动的蒸汽限制冷凝水向RPV回流,这可能会影响堆芯冷却,必须加以防止。以3D效果为主的逆流限流条件的模拟需要使用计算流体力学(CFD)方法。这些数值方法尚未成熟,因此需要专用的实验数据来进行验证。为了研究复杂反应堆典型几何形状中的两相流动行为,并为CFD代码验证提供合适的数据,在德累斯顿-罗斯森多夫(FZD)建立了“热腿模型”。此设置专用于光学测量技术,因此,选择了扁平测试部分设计,其宽度为50 mm。测试部分的轮廓以1:3的比例(即250 mm的通道高度)代表德国Konvoi PWR的热腿。测试部分安装在两个分离器之间,一个分离器模拟RPV,另一个分离器连接到蒸汽发生器的进气室。热腿模型在FZD的TOPFLOW设施的压力容器中在压力平衡下运行。本文介绍的空气/水实验的重点是在室温和最高3 bar的压力下,在立管和蒸汽发生器进气室区域内观察到的流动结构。进行的高速观测显示了分层界面的演变以及两相混合物(液滴和气泡)的分布。使用分离器中测得的水位变化对逆流限制进行了定量。与图像的对立表示,水淹的开始与热段水平部分中流动的逆转相吻合。此后,会产生更大的波浪,并发展成。此外,将从实验中获得的洪水点与文献中的经验相关性进行了比较。与先前的工作相比,获得了良好的总体一致性,而在较低的气体Wallis参数值下发现了零渗透。该偏差可归因于热腿模型的矩形横截面。

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