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

机译:管束中两相流流动的流体动力学和裸声道

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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:所提出的工作的重点是严重的事故情景,其中蒸汽发生器管破裂与核心损坏相结合,在加压水反应器(PWR)初级环中发生。核心损坏伴随着来自燃料元件的放射性气溶胶和碘种类的释放。如果蒸汽发生器的次级侧填充有水,则由于与水的相互作用,可以部分地除去气溶胶和碘。建立了测试设施三钽(蒸汽发生器多相流动调查中的管破裂),用于实验描述所描述的情景的流体动力学的实验研究。 Tristan是一种在环境温度和压力下操作的蒸汽发生器束的样机。对于裸池测试,可以删除捆绑包。淹水蒸汽发生器的液体库存使用脱矿质水进行建模。两层电线网传感器(WMS)(120×120线)直接构建到束中,为流动结构提供高分辨率数据。目标是研究气体和液体之间的界面面积的动态,这是两相流中传输现象表征的关键参数。实验允许我们研究流体动力学,用于距离断裂位置和不同气体流速的距离增加,并在管束和池中的流动之间进行比较。先前研究了管束对保留放射性气溶胶的意义。当存在管束时,气溶胶更有效地保留。如果没有详细了解潜在的流体动力学,特别是在界面区域,则无法确定导致保留增加的影响的最终结论。此外,这项工作开发了WMS数据的数据分析方法。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量成像技术,所以可以测量关于平均空隙分数及其标准偏差以及关于接口速度和界面区域浓度的动态信息的信息。所选择的情况覆盖注射位置和传感器之间的一个距离,即625mm,两个气流率为50kg / h和250kg / h。

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