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THE HYDRODYNAMICS OF TWO-PHASE FLOW IN A TUBE BUNDLE AND A BARE CHANNEL

机译:管束和裸露通道内两相流的水动力

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The focus of the presented work is a severe accident scenario in which a steam generator tube rupture combined with core damage occurs in a Pressurized Water Reactor (PWR) primary loop. The core damage is accompanied by the release of radioactive aerosols and iodine species from the fuel elements. If the secondary side of the steam generator is filled with water, the aerosols and iodine may be partially removed due to interactions with the water. The test facility TRISTAN (Tube Rupture In Steam generaTor multi-phAse flow iNvestigations) was built for the experimental investigation of the hydrodynamics of the described scenarios. TRISTAN is a mockup of a steam generator bundle that is operated at ambient temperature and pressure. For bare pool tests, the bundle can be removed. The liquid inventory of the flooded steam generator is modeled using demineralized water. Two layers of a wire-mesh sensor (WMS) (120 × 120 wires) are built directly into the bundle, which provides high-resolution data for the flow structure. The goal is to study the dynamics of the interfacial area between gases and liquid, which is a key parameter for the characterization of transport phenomena in two-phase flow. The experiments allow us to study the hydrodynamics for an increasing distance from the break location and different gas flow rates and to make comparisons between the flows in tube bundles and pools. The significance of the presence of a tube bundle on the retention of radioactive aerosols was investigated previously. Aerosols are retained more efficiently when a tube bundle is present. Without a detailed understanding of the underlying hydrodynamics especially in the interfacial area, final conclusions on the effects that cause an increase in retention cannot be determined. Additionally, this work develops the data analysis methodology for the WMS data. Therefore, a novel technique was used for the first time for the measurement of the interfacial area concentration (IAC). In this paper, a comparison between the tube bundle and the bare pool experiments is presented. Because the WMS is a flow imaging technique with high temporal and spatial resolution, information regarding the averaged void fractions and its standard deviation as well as kinetic information regarding the interface velocity and interfacial area concentration can be measured. The selected cases cover one distance between the injection location and the sensor, namely, 625 mm, and two gas flow rates of 50 kg/h and 250 kg/h.
机译:提出的工作的重点是严重的事故情况,在该事故中,在压水堆(PWR)的主回路中发生蒸汽发生器管破裂并伴有堆芯损坏的情况。核心损害伴随着燃料元件中放射性气溶胶和碘物质的释放。如果蒸汽发生器的次级侧充满水,由于与水的相互作用,气溶胶和碘可能会被部分去除。建立了测试设施TRISTAN(蒸汽发生多相流中的管道破裂研究),用于实验研究所描述情景的水动力。 TRISTAN是在环境温度和压力下运行的蒸汽发生器束的模型。对于裸池测试,可以删除捆绑软件。使用软化水对淹没式蒸汽发生器的液体存量进行建模。线束中直接内置了两层线网传感器(WMS)(120×120线),可为流结构提供高分辨率数据。目的是研究气体和液体之间的界面区域的动力学,这是表征两相流中传输现象的关键参数。实验使我们能够研究距断裂位置越来越远的流体动力学和不同的气体流速,并能对管束和池中的流动进行比较。先前已经研究了管束的存在对放射性气溶胶保留的重要性。当存在管束时,气雾剂可以更有效地保留。如果没有详细了解潜在的流体动力学,尤其是在界面区域,就无法确定导致滞留量增加的最终结论。此外,这项工作为WMS数据开发了数据分析方法。因此,首次使用一种新技术来测量界面面积浓度(IAC)。本文提出了管束与裸池实验之间的比较。因为WMS是具有高时间和空间分辨率的流动成像技术,所以可以测量有关平均空隙率及其标准偏差的信息以及有关界面速度和界面区域浓度的动力学信息。所选案例涵盖了注射位置和传感器之间的一个距离,即625 mm,以及两种分别为50 kg / h和250 kg / h的气体流量。

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