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HYDRODYNAMICS OF PARTIAL NUCLEATE BOILING BY PIV TECHNIQUE

机译:PIV技术部分核心沸腾的流体动力学

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Presented investigation treats convective effects of ebullition cycle in a partial nucleate boiling regime. During the ebullition cycle the bubble induces considerable flows of liquid phase in its vicinity. To quantify these flows the partial nucleate boiling on single nucleation site has been investigated experimentally using PIV technique. After inception the bubble interface passes through five different stages. These stages are: hemispherical expansion, vertical elongation, base shrinking, bubble departure and rising. Liquid phase movement induced by rising bubble is well-known as a drift flow phenomenon. Rising bubble convection during the waiting time has been recognized as the most important stage of ebullition cycle for the heat transfer assessment. Unsteady velocity distribution of drift flow in close vicinity of the boiling surface has been analyzed using flow field data acquired by PIV. Vertical and radial velocity distributions caused by rising bubbles grouped in three different morphological groups are presented graphically along marked surface parallel with boiling plate. At the end the governing heat transfer mechanisms in the bubble influence area are treated briefly.
机译:提出的调查对沸腾循环在部分成核沸腾制度中的对流影响。在沸腾循环期间,气泡在其附近诱导相当大的液相流。为了量化这些流动,使用PIV技术通过实验研究了单核核心位点上的部分成核沸点。初始后,气泡接口通过五个不同的阶段。这些阶段是:半球形膨胀,垂直伸长率,基地萎缩,泡沫脱落和上升。上升气泡引起的液相运动是众所周知的漂移流动现象。在等待时间期间的泡影对流上升被认为是传热评估的沸腾周期最重要的阶段。使用PIV获取的流场数据分析了沸点附近的漂移流程的不稳定速度分布。沿着三种不同形态组分组的泡沫升高引起的垂直和径向速度分布在图形上沿着与沸板平行的标记表面呈现。在结束时,气泡影响面积中的控制传热机制是短暂的。

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