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首页> 外文期刊>International Journal of Heat and Mass Transfer >Two-phase flow frictional pressure drop prediction in helical coiled tubes
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Two-phase flow frictional pressure drop prediction in helical coiled tubes

机译:螺旋卷绕管中的两相流摩擦压降预测

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Based on the construction of different experimental databases, the frictional pressure drop in helical tubes for single-phase and water-steam two-phase flow was analyzed empirically. The aim of the present study is to provide the scientific community with a reliable and simple to use predictive tool for estimating frictional pressure drop in helical tubes covering operating conditions of interest for the design and operation of coiled tube once-through steam generators, as those used in small modular advanced nuclear reactors. The single-phase database contains around 2000 data points from 14 different sources, including data measured with air and water as working fluids, covering Reynolds numbers ranging from 40 to 145,000 and curvatures between 0.0027 and 0.3. The prediction capability of some existing correlations for simple phase flow was analyzed, concluding that Ito correlations for laminar and turbulent regime (1959) are the best ones fitting the experimental data. The average difference between experimental data and Ito correlations was 3.75% for laminar regime and 2.11% for turbulent regime. The two-phase flow database was built with data available from open literature works. Due to the fact no existing correlation was found to successfully predict the available data, a new prediction tool based on the homogeneous equilibrium model was developed for water-steam flows at conditions of interest. The proposed tool, so-called FEMA correlation, converges to the Ito correlations for single phase flow, i.e. for thermodynamic qualities equal to 0 and 1. In addition, the correlation successfully fits the experimental data with an average error of 7.4% which is smaller than any other existing correlation. In addition, the new correlation is recommended for water-steam flow in vertical helical tubes with liquid only Reynolds numbers ranging from 20000 and 124000, pressures between 1 and 8 MPa, curvatures between 0.01 and 0.08, and thermodynamic qualities ranging from 0 to 1.
机译:基于不同实验数据库的构造,经验分析了单相和水蒸气两相流动螺旋管中的摩​​擦压降。本研究的目的是提供科学界,可靠且简单地利用用于估算螺旋管中的摩​​擦压降,涵盖卷绕管道的螺旋管中的摩​​擦压力下降,作为螺旋管的设计和操作的操作条件,如那些用于小型模块化晚期核反应堆。单相数据库包含大约2000个不同来源的数据点,包括用空气和水作为工作流体测量的数据,覆盖从40到145,000的雷诺数,0.0027和0.3之间的曲率。分析了一些现有的简单相流相关性的预测能力,得出结论是层流和湍流制度(1959)的ITO相关性是拟合实验数据的最佳选择。对于湍流制度,实验数据和ITO相关性的平均差异为3.75%,2.11%。两阶段流量数据库由开放文献工作中提供的数据构建。由于发现没有发现现有相关性成功预测可用数据,开发了一种基于均匀平衡模型的新预测工具,用于感兴趣条件下的水蒸汽流动。所提出的工具,所谓的FEMA相关性,收敛于单相流的ITO相关性,即用于等于0和1的热力学质量。此外,相关性成功适合实验数据,平均误差为7.4%比任何其他现有相关性。此外,建议新相关性用于垂直螺旋管中的水蒸汽流量,液体只有20000和124000的雷诺数,在1到8MPa的压力之间,0.01和0.08之间的曲率,以及从0到1的热力学品质。

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