原子能科学技术2012，Vol.46Issue(1)：51-56,6.
蒸汽发生器二次侧汽液两相流数值模拟
Numerical Simulation on Vapor-Liquid Two-Phase Flow of the Secondary Circuit in Steam Generator
摘要
Abstract
Taken the steam generator of Daya Bay Nuclear Power Station as the prototype, the "unit pipe" three-dimensional physical model of steam generator was established under the guidance of the similarity principle. Adopting Particle model and thermal phase change model, numerical simulation was implemented on two-phase flow and boiling heat transfer characteristics of the secondary circuit in steam generator based on CFX software. The results show that heat transfer coefficient and cross-section void fraction increase along the height of tubes at full load. The error of average heat transfer coefficient is 8. 4% between numerical simulation and Rohsenow empirical correlation. The export mass fraction is consistent with the actual operating parameters of Daya Bay Nuclear Power Station. The successful application of thermal phase change model to two-phase flow numerical simulation of the steam generator can supply reference for thermal-hydraulic accurate analysis of the steam generator.关键词
蒸汽发生器/汽液两相流/Particle模型/热相变模型Key words
steam generator/vapour-liquid two phase flow/Particle model/thermal phase change model分类
能源科技引用本文复制引用
杨元龙,孙宝芝,杨龙滨,张羽..蒸汽发生器二次侧汽液两相流数值模拟[J].原子能科学技术,2012,46(1):51-56,6.基金项目
中国博士后科学基金面上资助项目(20100471017) （20100471017）
黑龙江省博士后科学基金资助项目(LBH-Z09233) （LBH-Z09233）
国家自然科学基金资助项目(51109048) （51109048）
