钠冷快堆直流蒸汽发生器跨尺度耦合分析

Cross-scale Coupling Analysis of Once-through Steam Generator of Sodium-cooled Fast Reactor

  • 摘要: 直流蒸汽发生器(OTSG)中存在全流型沸腾换热、两侧耦合换热及结构复杂且尺寸跨度大等特征,使得采用计算流体力学(CFD)与三维精细化建模方法分析包含大规模换热管束的OTSG三维温度场时面临计算难度高、求解效率低和求解稳定性差等问题。本文基于全流型沸腾传热模型与流型判别模型,以印度快堆直流蒸汽发生器测试模型(SGTF)为研究对象,建立了管侧从过冷水到过热蒸汽的一维全流型沸腾传热模型及其与壳侧三维精细化CFD模型的跨尺度耦合求解模型,实现了OTSG每根换热管与壳侧三维流体域的独立耦合,并开展了堵管分析。通过与实验数据的对比分析验证了该方法的有效性。研究结果表明:采用管侧一维全流型沸腾传热模型与壳侧三维CFD模型的跨尺度耦合方法,可准确预测每根换热管全高度上的温度分布及主要传热特征点,能获得不同换热管及管壁之间的温度差,且易于实现堵管分析;跨尺度耦合求解方法避免了直接采用三维多相流模型,大幅提高了OTSG三维温度场的求解效率及稳定性。本文研究为OTSG的设计与安全校核提供了一种高效的三维精细化数值分析方法。

     

    Abstract: There are a series of complex physical phenomena in once-through steam generators (OTSG), such as full-regime flow boiling and phase-change heat transfer from supercooled water to superheated steam, coupled heat transfer between tube side and shell side. At the same time, the structure of OTSG is also very complex. There are a large number of slender heat exchange tubes in the OTSG, and the difference between the radial size and the axial size is very large, that is, the size span is large. These problems and characteristics lead to the problems of high computational difficulty, low solution efficiency and poor solution stability when using computational fluid dynamics (CFD) and threedimensional refined modeling methods to analyze the three-dimensional temperature field of OTSG with large-scale heat exchange tube bundles. Based on the full-regime flow boiling, phase-change heat transfer model and the criterion model of boiling flow regime, a one-dimensional full-regime flow boiling and phase-change heat transfer analytical model were stablished in this paper. With appropriate parameter transfer, the cross-scale coupling solution between the one-dimensional boiling heat transfer analytical model on the tube side and the three-dimensional refined CFD model on the shell side was realized. This crossscale coupling calculation method can realize the independent coupling between each heat exchange tube on the water side and the threedimensional fluid domain on the sodium side. The proposed crossscale coupling numerical model was applied to the oncethrough steam generator of the Indian fast reactor to realize the independent coupling between each OTSG heat exchange tube and the shell side threedimensional sodium fluid domain, and the plugged tube condition analyses were carried out. The effectiveness of the proposed cross-scale coupling model was verified by comparison with experimental data. The study results show that the established crossscale coupling numerical analysis model between tube side and shell side can accurately predict the temperature distribution and the main heat transfer characteristic points of each heat exchange tube over the entire height. The calculation results can also give the temperature of different heat exchange tubes and the temperature difference between the tube walls of each heat exchange tube in detail. This method is also very convenient to realize the analysis of plugging conditions. The crossscale coupling solution method avoids the direct solution of complex threedimensional multiphase flow equations, and greatly improves the efficiency and stability of the numerical solution of the OTSG threedimensional temperature field. This study provides an efficient threedimensional refined analysis method for the design and safety verification of OTSG.

     

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