原子能科学技术2018，Vol.52Issue(4)：590-599,10.DOI:10.7538/yzk.2017.youxian.0426
螺旋管核态沸腾两相流摩擦压降与传热数值分析
Numerical Simulation of Two-phase Flow Friction Pressure Drop and Heat Transfer for Nucleate Boiling in Helically Coiled Tube
摘要
Abstract
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.关键词
蒸汽发生器/螺旋管/两相流/摩擦压降Key words
steam generator/helically coiled tube/two-phase flow/friction pressure drop分类
能源科技引用本文复制引用
赵宇,孙宝芝,鲍杰,于祥,史建新,张鹏..螺旋管核态沸腾两相流摩擦压降与传热数值分析[J].原子能科学技术,2018,52(4):590-599,10.基金项目
国家自然科学基金资助项目(51479040,51579048,51709249) （51479040,51579048,51709249）
