螺旋管核态沸腾两相流摩擦压降与传热数值分析

通过合理简化一体化模块式先进反应堆(SMART)螺旋管式蒸汽发生器，建立螺旋管单元管模型，采用两流体模型和非平衡过冷沸腾模型，在均匀热流密度下对螺旋管内流体进行不同参数下流动与传热数值模拟。结果表明：摩擦压降数值计算结果与陈学俊经验公式最为接近；曲率从0.04降至0.012时，摩擦压降明显下降，曲率继续下降，摩擦压降不变；加速压降几乎不受曲率影响；螺旋升角为3°～8.6°时，计算摩擦压降可不考虑螺旋升角的影响；雷诺数越大，总压降和摩擦压降均变大，摩擦压降梯度也明显增大。

Numerical Simulation of Two-phase Flow Friction Pressure Drop and Heat Transfer for Nucleate Boiling in Helically Coiled Tube

Through the rationally simplifying helically coiled tube steam generator of the system integrated modular advanced reactor (SMART), the single-tube model of helically coiled tube steam generator was established. Based on two fluids model and non equilibrium subcooled boiling model, the flow and heat transfer process in the helically coiled tube under different parameters for the steam generator was numerically simulated with constant heat flux. The results show that the numerical results of friction pressure drop are the closest to Chen Xuejun’s correlation. When the curvature decreases from 0.04 to 0.012, the friction pressure drop decreases significantly, but the friction pressure drop does not change as the curvature below 0.012. The acceleration pressure drop is almost unaffected by curvature. The calculated friction pressure drop is not affected when the angle varies from 3° to 8.6°. The total pressure drop and the friction pressure drop increase with Reynolds number, while the friction pressure drop gradient increases obviously.