摘要
以大亚湾核电站蒸汽发生器为原型,在相似原理的指导下,建立了蒸汽发生器"单元管"三维物理模型,采用Particle模型和热力学相变模型,并基于CFX软件实现了蒸汽发生器二回路侧两相流流动与沸腾换热特性数值模拟。计算结果表明:满负荷运行时,沿传热管高度升高,蒸汽发生器的传热系数及截面含汽率均呈上升趋势,其平均传热系数的数值模拟结果与Rohsenow经验关联式计算结果间的误差为8.4%,出口质量含汽率与大亚湾核电站实际运行参数相符。热相变模型在蒸汽发生器两相流数值模拟中的成功应用,可为蒸汽发生器热工水力的准确分析提供参考。
Taken the steam generator of Daya Bay Nuclear Power Station as the proto- type, the ＂unit pipe＂ three-dimensional physical model of steam generator was estab- lished under the guidance of the similarity principle. Adopting Particle model and ther- mal 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.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2012年第1期51-56,共6页
Atomic Energy Science and Technology
基金
中国博士后科学基金面上资助项目(20100471017)
黑龙江省博士后科学基金资助项目(LBH-Z09233)
国家自然科学基金资助项目(51109048)
