共查询到16条相似文献,搜索用时 234 毫秒
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采用双流体模型对高压高过冷度下垂直圆管中水的过冷流动沸腾进行了数值模拟。通过对比不同气泡直径模型,揭示了气泡直径对于壁面传热方式的影响,确定了适合高压工况的气泡直径模型。考察了压力及壁面热通量对流动及传热特性的影响。计算结果表明,压力增加气泡脱离直径减小,单相对流传热所占比例增加,表面传热系数减小。高压高过冷度特征决定了气泡相分布极不均匀,随着热通量的增加,壁面附近容易形成气泡的密集,对过冷流动沸腾中的传热特性有重要影响。 相似文献
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以去离子水为实验工质,在窄缝宽度δ=3、4 mm,质量流速G=143、300 kg·m-2·s-1,主流过冷度ΔTsub=17、25℃,热通量q=1~20 W·cm-2的参数范围内,对常压下竖直窄缝通道内向上流动过冷沸腾的换热规律进行了实验研究。对不同宽度窄缝通道内的同一区域过冷沸腾气泡演变过程进行了可视化实验分析,发现窄缝宽度因素对过冷流动沸腾的流动换热特性和壁面核化特性影响显著,其中包括沸腾起始点ONB,压降ΔP,传热系数h,汽化核心密度Na,气泡脱离直径Dd,气泡脱离频率f等。 相似文献
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研究气泡浮升直径对揭示过冷流动沸腾的传热机理至关重要。为探究流动工况对气泡浮升直径的影响机制,针对发动机缸盖沸腾区域的冷却通道设计了一个水动力相似的矩形实验通道,搭建了过冷流动沸腾可视化实验循环系统。基于该可视化实验系统,研究了系统压力、壁面过热度、流速以及液体过冷度对气泡浮升直径的影响,发现气泡浮升直径随着系统压力、流速以及过冷度的增大而变小,随着壁面过热度的增大而增大。建立了气泡在浮升时刻的力平衡模型,该力平衡模型的预测值与实验值的平均相对误差为12.25%。为了便于工程应用,基于气泡浮升直径的力平衡模型,建立了气泡浮升直径的经验模型,该经验模型的预测值与实验值的平均相对误差为6.80%。 相似文献
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准确预测直流蒸汽发生器流动沸腾及蒸干对其设计、安全可靠运行极其重要。通过对B&W公司直流蒸汽发生器进行合理简化,引入两流体三流场数学模型及壁面热通量分区模型,分别进行基于常热通量和耦合传热的蒸汽发生器流动沸腾数值模拟。结果表明:蒸干发生时传热性能急剧下降,常热通量边界下壁温升高的幅度相当大(约300 K·m-1),而耦合传热边界下壁温飞升幅度约为25 K·m-1,与实际情形相一致;两种热边界中预热区会发生过冷沸腾,壁面处传热由液相对流换热、淬火换热和蒸发换热3部分构成,核态沸腾区蒸发换热为主要换热方式,同时伴随着液相对流换热和淬火换热,蒸干发生时淬火换热和蒸发换热全部降到0,在蒸干后传热区域换热方式为气相对流换热。 相似文献
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《化工学报》2016,(Z1)
准确预测直流蒸汽发生器流动沸腾及蒸干对其设计、安全可靠运行极其重要。通过对BW公司直流蒸汽发生器进行合理简化,引入两流体三流场数学模型及壁面热通量分区模型,分别进行基于常热通量和耦合传热的蒸汽发生器流动沸腾数值模拟。结果表明:蒸干发生时传热性能急剧下降,常热通量边界下壁温升高的幅度相当大(约300K·m~(-1)),而耦合传热边界下壁温飞升幅度约为25K·m~(-1),与实际情形相一致;两种热边界中预热区会发生过冷沸腾,壁面处传热由液相对流换热、淬火换热和蒸发换热3部分构成,核态沸腾区蒸发换热为主要换热方式,同时伴随着液相对流换热和淬火换热,蒸干发生时淬火换热和蒸发换热全部降到0,在蒸干后传热区域换热方式为气相对流换热。 相似文献
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Multiple size group (MUSIG) model combined with a threedimensional twofluid model were em ployed to predict subcooled boiling flow of liquid nitrogen in a vertical upward tube. Based on the mechanism of boiling heat transfer, some important bubble model parameters were amended to be applicable to the modeling of liquid nitrogen. The distribution of different discrete bubble classes was demonstrated numerically and the distribu tion patterns of void fraction in the wallheated tube were analyzed. It was found that the average void fraction in creases nonlinearly along the axial direction with wall heat flux and it decreases with inlet mass flow rate and sub cooled temperature. The local void fraction exhibited a Ushape distribution in the radial direction. The partition of the wall heat flux along the tube was obtained. The results showed that heat flux consumed on evaporation is the leading part of surface heat transfer at the rear region of subcooled boiling. The turning point in the pressure drop curve reflects the instability of bubbly flow. Good agreement was achieved on the local heat transfer coefficient aalnst experimental measurements, which demonstrated the accuracy of the numerical model. 相似文献
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沸腾传热及气液两相流动都是常见的物理现象,其流动形式及传热机理复杂.文章借助于CFX流体计算平台,模拟了水在三维竖直圆管内的过冷流动沸腾过程,给出管内流体状态参数的变化规律.得到沿管长的气相体积分数的变化规律,沿管长沸腾传热系数的变化趋势,明显地看到沸腾对传热的强化作用,得到径向液体温度分布情况.对过冷流动沸腾的内在机... 相似文献
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分析了液氮流动沸腾过程中气液两相间动量、能量以及质量的传输规律,建立了相应的理论模型,新模型重点修正了界面面积浓度和气泡挣脱直径的计算式;采用新建立的理论模型作为封闭方程对CFX-4.3中内建的双流体模型进行了修正,并采用修正后的双流体模型模拟了液氮在垂直圆管内的流动沸腾过程.数值模拟的结果与文献中的实验数据吻合较好,证明了本文所建模型的合理性.通过数值模拟发现,两相流参数分布的不均匀性对液氮流动沸腾过程中的热质传输特性有重要影响. 相似文献
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The Eulerian two-phase boiling model of the subcooled boiling of coolant in a 3 × 3 fuel assembly is established and compared with the experimental data to verify its accuracy. The effects of four shapes of bow deformation on subcooled boiling flow and heat transfer characteristics are obtained by comparing and analyzing the distributions of thermal–hydraulic parameters, including the axial wall superheat, liquid phase temperature, axial void fraction, various heat fluxes, heat transfer coefficient, and turbulent kinetic energy. All shapes of bow deformation will lead to the redistribution of coolant among different subchannels, and the distributions of thermal–hydraulic parameters would be greatly affected. The bow deformation of fuel rod easily causes local boiling, which results in local high temperature of liquid phase and bubble accumulation, and a decrease in the area of high liquid phase heat transfer coefficient on the surface of bowing fuel rod. Additionally, the non-uniform distribution of turbulent kinetic energy caused by bow deformation in different axial sections not only affects the heat transfer performance of coolant, but also causes the increment in pressure drop, which has negative effects on the safe operation of the nuclear reactor. This paper can provide data and theoretical support for engineering design. 相似文献