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A pragmatic approach for simulating the fluid flow and heat transfer within industrial evaporator vessels

机译:一种实用的方法来模拟工业蒸发器容器内的流体流动和传热

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This article presents a pragmatic method for simulating the fluid flow and heat transfer in low-pressure, industrial evaporator systems. The method couples a single phase computational fluid dynamics model with an empirical correlation in order to account for the thermal effects of boiling. Due to the time-constraints often associated with industrial modelling, the method here is developed with the intention that rapid predictions of thermal and flow behaviour can be obtained to inform plant operators of the impact of changing evaporator process and operational configuration within the nuclear industry.The presented model results are compared against data obtained from an experimental rig of a scaled evaporator test section, based at Heriot-Watt University, UK. Tests operate at near-vacuum conditions (5 kPa) and experience a variety of heat transfer regimes, whereby portions of the rig are convectively heated and other regions undergo sub-cooled nucleate boiling.A mesh sensitivity study is performed in order to determine the optimal computational grid size, and demonstrate a sufficient level mesh independence, this is quantified using the GCI method. Additionally, a turbulence sensitivity study is carried out for a number of operational configurations. Finally, various boiling correlations are tested in order to determine the optimal correlation for the application here.Results in this work show that the modelling approach developed predicts temperatures in the various different regions of the rig well, also good agreement is achieved with the experimental data when using the Launder-Sharma K-Epsilon model (Launder and Sharma, 1974). In regions which were predicted to boil, it was found the Gorenflo nucleate boiling correlation (Gorenflo and Kenning, 2009) gave a good all-round approximation to the experimental temperatures. Crown Copyright (C) 2019 Published by Elsevier Ltd. All rights reserved.
机译:本文提出了一种实用的方法,用于模拟低压工业蒸发器系统中的流体流动和传热。该方法将单相计算流体动力学模型与经验相关性结合起来,以解决沸腾的热效应。由于通常与工业建模相关的时间限制,因此开发此方法的目的是,可以快速预测热和流动行为,以告知工厂运营商核工业中蒸发器工艺和运行配置的变化所带来的影响。将呈现的模型结果与从英国Heriot-Watt大学的规模化蒸发器测试部分的实验装置获得的数据进行比较。测试在接近真空的条件下(5 kPa)进行,并经历了多种传热方式,对钻机的部分进行对流加热,而其他区域则进行过冷的核沸腾。计算网格大小,并证明足够的水平网格独立性,这可以使用GCI方法进行量化。另外,针对多种操作配置进行了湍流敏感性研究。最后,为了确定最佳沸腾相关性,对各种沸腾相关性进行了测试。工作结果表明,所建立的建模方法可以预测钻机井不同区域的温度,并且与实验数据也取得了很好的一致性。当使用Launder-Sharma K-Epsilon模型时(Launder和Sharma,1974年)。在预计会沸腾的区域中,发现Gorenflo核沸腾相关性(Gorenflo和Kenning,2009年)为实验温度提供了很好的全方位近似。 Crown版权所有(C)2019,由Elsevier Ltd.出版。保留所有权利。

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