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Sensitivity study of momentum and turbulence models for subcooled boiling phenomena simulation
Journal of the Brazilian Society of Mechanical Sciences and Engineering ( IF 2.2 ) Pub Date : 2020-07-28 , DOI: 10.1007/s40430-020-02500-5
Brian de Lima Curtt , Francisco A. Braz Filho

This sensitivity analysis of the momentum and turbulence equations uses the Eulerian two-phase approach and intends to achieve a validated modeling for subcooled boiling flows. The studied regime is relevant to many industry applications and to the critical heat flux phenomenon, an important process for design and safety analyses of water-cooled nuclear power plants. Ascending water flows in heated circular pipes are modeled under subcooled boiling condition and applying a combination of computational multi-fluid dynamics (CMFD) models, each one for the estimation of specific terms of the governing equations. Turbulence closure, drag, lift, turbulent interaction, turbulent dispersion, wall lubrication and interfacial area models are investigated through variations around a reference model set defined based on the literature review, changing each model one at a time to study their impacts on the simulation results. Key parameters, such as void fraction and temperature profiles, are chosen for the evaluation of the results. Despite the difficulty of tracking the contributions of simultaneously applied models, the Legendre–Magnaudet lift force and the Burns et al. turbulent dispersion force models show good agreement with the experimental data of a flow at 4.5 MPa used for the quality verification of the simulations. These models are also applied for flows with pressures ranging from 1.5 to 15 MPa, and they lead to promising results. This study gives interesting insights on the influence of the distinct models composing momentum and turbulence calculations, contributing to the validation effort of the CMFD approach for subcooled boiling flows.



中文翻译:

模拟过冷沸腾现象的动量和湍流模型的敏感性研究

对动量和湍流方程的敏感性分析使用欧拉两相方法,旨在为过冷沸腾流建立经过验证的模型。研究方案与许多工业应用以及临界热通量现象有关,这是水冷核电站设计和安全分析的重要过程。在过冷沸腾条件下,对加热的圆形管道中的上升水流进行建模,并应用计算多流体动力学(CMFD)模型的组合,每个模型用于估计控制方程的特定项。湍流闭合,阻力,升力,湍流相互作用,湍流扩散,壁润滑和界面面积模型是通过围绕文献综述定义的参考模型集周围的变化进行研究的,一次更改每个模型以研究它们对模拟结果的影响。选择关键参数,例如空隙率和温度曲线,以评估结果。尽管很难跟踪同时应用的模型的贡献,但Legendre–Magnaudet升力和Burns等人。湍流分散力模型与用于模拟质量验证的4.5 MPa流量的实验数据显示出良好的一致性。这些模型还适用于压力范围为1.5到15 MPa的流量,它们带来了可喜的结果。这项研究对组成动量和湍流计算的不同模型的影响提供了有趣的见解,有助于对过冷沸腾流的CMFD方法的验证工作。

更新日期:2020-07-28
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