摘要
基于相似模化理论建立了蒸汽发生器一、二回路流体及传热管流-固耦合传热的单元管三维物理模型,对大亚湾核电厂蒸汽发生器不同工况下的热工水力稳态特性进行了数值模拟研究。采用热相变模型描述二回路汽液两相流动与换热、流-固耦合模型描述一回路冷却剂借助U型管与二回路流体换热。数值计算结果表明:满负荷运行时,传热管内壁温度变化趋势与一次侧流体基本一致,外壁温度与二次侧流体温度变化趋势相同;截面平均含汽率沿传热管高度的升高呈上升趋势,出口质量含汽率与大亚湾核电厂实际运行参数相符;随负荷降低一回路出口温度基本不变,二回路出口温度升高,质量含汽率及传热系数下降,平均传热系数与Rohsenow经验关联式的计算结果基本吻合。
Three-dimensional unit pipe physical model of fluid-solid coupling heat transfer on primary side fluid,secondary side fluid and tubes in the steam generator was established based on the similarity and modeling principle.Thermal-hydraulic steady-state characteristics of the steam generator of Daya Bay Nuclear Power Plant were investigated by numerical simulation under different operating conditions.Thermal phase change model was utilized to describe vapor-liquid two-phase flow and heat transfer,and heat transfer between primary side coolant and secondary side fluid through the tubes was calculated by fluid-solid coupled model.Numerical results show that tube inner wall temperature distribution profile is almost identical with that of primary side fluid at a full power,and so is secondary side fluid with the outer wall.Cross-section average void fraction increases along the height of tubes and the outlet mass fraction of vapor is consistent with the actual operating value of Daya Bay Nuclear Power Plant.With the power load lowering down,the primary outlet temperature maintains almost unchanged,the outlet temperature of the secondary side increases,but both the outlet mass fraction and heat transfer coefficient of vapor decrease.The average heat transfer coefficient is basically consistent with the result of Rohsenow empirical correlation.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2013年第5期761-767,共7页
Atomic Energy Science and Technology
基金
国家自然科学基金资助项目(51109048)
黑龙江省博士后科学基金资助项目(LBH-Z09233)
中国博士后科学基金面上资助项目(20100471017)
关键词
蒸汽发生器
耦合传热
稳态特性
数值模拟
steam generator
coupled heat transfer
steady-state characteristic
numerical simulation
