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Flow Regime Observations in a Vertical Annulus with an Inner Roughened Tube

机译:带有内部粗管的垂直环空流态观测

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The efficiency and safe performance of a nuclear power plant is often reliant upon a solid understanding of the multiphase flow phenomena that occurs in various components and piping networks throughout the heat transport loops. Depending upon the conditions, various flow regimes can be observed and each of these flow regimes would have a different impact upon the heat transfer and pressure drop of the component or piping that the two-phase mixture is traveling in. Thus, many researchers have performed significant studies to predict flow regime.Over the past several years, the maintenance and inspection efforts at various nuclear power plants have shown that ageing phenomena are occurring including corrosion, cracking, erosion phenomena, and deposition of materials. One of the effects of such phenomena is the roughening of the surface which would impact the nature of fluid behaviour, heat transfer behaviour, and mass transfer at the surface. Relationships for surface conditions and pressure drop/heat transfer are already established for single phase flow conditions albeit with significant uncertainty. Yet, the relationships for multiphase flow have not been established and it is assumed that the surface effects are covered through the single phase component.In this work, experimental studies are performed for a vertical annulus geometry. The apparatus consists of glass tubing to allow visualization of the flow regime inside the tubes. The glass tube material is also a reference case for the smooth tube. Experiments are performed in a bubble column mode for superficial gas velocities up to 0.5m/s. Observations are taken at various developing lengths and varied water inventories. The results are compared to previous work which shows that the smooth tube results match previous measurements.The inner surface of the tube is modified by forming a thin layer of material over the glass surface. The material is initially moldable and allows for the imprinting of different surface shapes and roughnesses. The material cures in a few hours and is resistant to erosion or dissolution in water. Thus, the surface conditions are changed on the inner tube.The experiments indicate that the flow regime transition from bubbly to slug flow and from slug to churn flow occur at lower superficial gas velocities.
机译:核电厂的效率和安全性能通常取决于对热传递回路中各个组件和管道网络中发生的多相流现象的扎实了解。根据条件,可以观察到各种流态,并且这些流态中的每一种都会对两相混合物所进入的组件或管道的传热和压降产生不同的影响。因此,许多研究人员进行了研究预测流动状态的重要研究。 在过去的几年中,各个核电厂的维护和检查工作表明,老化现象正在发生,包括腐蚀,破裂,腐蚀现象和材料沉积。这种现象的影响之一是表面的粗糙化,这将影响流体行为,传热行为和表面质量转移的性质。尽管存在很大的不确定性,但已经为单相流动条件建立了表面条件与压降/传热之间的关系。但是,尚未建立多相流的关系,并假设通过单相成分覆盖了表面效应。 在这项工作中,对垂直环面几何形状进行了实验研究。该设备由玻璃管组成,以可视化管内的流动状态。玻璃管材料也是光滑管的参考案例。实验在气泡塔模式下进行,表观气体速度高达0.5 小姐。在不同的发展时期和不同的水存量下进行观测。将结果与以前的工作进行比较,结果表明光滑管的结果与以前的测量结果相符。 管的内表面通过在玻璃表面上形成一层薄材料而得到改进。该材料最初是可模制的,并允许压印不同的表面形状和粗糙度。该材料可在数小时内固化,并且对水的侵蚀或溶解具有抵抗力。因此,内管的表面状况发生了变化。 实验表明,在较低的表观气速下,流态从泡状流向团状流以及从团状流向搅动流过渡。

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