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IMPLEMENTATION OF TWO-GROUP INTERFACIAL AREA TRANSPORT IN A ONE-DIMENSIONAL COMPUTATIONAL ENVIRONMENT

机译:在一维计算环境中实现两组界面区域运输

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A simplified one-dimensional computer code has been written which uses the two-fluid model to predict two-phase flows in large diameter vertical channels. Simplifying assumptions have been used to eliminate the energy equation and simplify the momentum equations. This code, written using MATLAB, uses a two-group momentum approach with two-group interfacial area transport to dynamically predict the development of the flow. This provides the ability to evaluate the interfacial area transport equation within a similar computational environment to that used in best estimate thermal-hydraulics analysis codes used in the nuclear industry and allows the evaluation of the performance of the transport equation, constitutive relations, bubble coalescence and breakup models, and other models using the same framework in which they will be used. The current version is limited to systems without phase change, i.e. where boiling and condensation are not significant. While the force-balance approach to interfacial drag has been used in the analyses presented, the code also includes a two-group drift-flux correlation and the implementation of the drag-coefficient approach recommended by Ishii and Hibiki as options within the code, allowing the comparison of various interfacial drag approaches. The code has been used to simulate the experiments performed by Shen et al in pipes with diameter of 0.2 m and length of 26.0 m. The code was able to duplicate the characteristic axial void fraction profile caused by the transition between the bubbly and cap-bubbly flow regimes in the experimental facility, showing that the two-group approach can be applied within the framework of existing best estimate codes. Further improvements to the accuracy of the code are expected if the bubble coalescence and breakup models are benchmarked based on a wider database and using the new approach to compute the flow development.
机译:已经写了一种简化的一维计算机代码,其使用双流体模型来预测大直径垂直通道中的两相流。简化假设已被用于消除能量方程并简化动量方程。使用MATLAB编写的此代码采用双组动量方法,具有双组界面区域传输,动态预测流动的发展。这提供了在核工业中使用的最佳估计热液压分析代码中评估类似计算环境中的界面区域传输方程的能力,并允许评估传输方程,构成关系,泡沫聚结的性能。分手模型,以及使用与其使用相同框架的其他模型。当前版本仅限于没有相位变化的系统,即沸腾和冷凝不显着。虽然在呈现的分析中使用了界面阻力的力平衡方法,但代码还包括两个组漂移通量相关性,并且ISHII和Hibiki推荐的拖动系数方法的实现作为代码中的选项,允许各种界面阻力方法的比较。该代码已用于模拟Shen等人在直径为0.2米和长度为26.0米的管道中进行的实验。该代码能够复制由实验设施中的气泡和帽子气相变化的转变引起的特征轴向空隙率分布曲线,表明双组方法可以应用于现有最佳估计代码的框架内。预期泡沫聚结和分手模型基于更广泛的数据库并使用新方法来计算流动开发,进一步改进代码的准确性。

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