摘要
为深入研究核电蒸汽发生器二回路侧汽液两相的沸腾传热和流动特性,采用RPI模型对过冷沸腾区域壁面的热流分配进行划分,以此修正CFD程序中的两流体模型,并利用文献中的实验结果验证了修正后模型的适定性.最后以大亚湾压水堆核电站为例,采用该模型对蒸汽发生器内二回路预热段单元通道内的过冷沸腾进行计算,获得了通道内流体空泡份额、速度、温度、热流量分配等的分布情况.
In order to deeply investigate the vapor-liquid two-phase boiling heat transfer and flow characteristics in the secondary circuit of steam generator, the wall heat flux partition in the subcooled boiling region was divided by using the RPI model for revising the two-fluid model of the CFD （Computational Fluid Dynamics ） program, and some published experimental results were used to validate the reliability of the revised mode. Moreover, a case study on the steam generator of Daya Bay PWR （ Pressurized Water Reactor） nuclear power plant was carried out, in which the subcooled boiling in the preheating part of the secondary circuit was computed with the revised model, and the distributions of fluid void fraction, speed, temperature and heat flux partition in the preheating part were all obtained.
出处
《华南理工大学学报（自然科学版）》
EI
CAS
CSCD
北大核心
2013年第5期87-92,共6页
Journal of South China University of Technology(Natural Science Edition)
基金
国家自然科学基金资助项目(10702020
51176052)
广东省科技攻关项目(2009B010900020)
华南理工大学中央高校基本科研业务费专项资金资助项目(2009ZM0279)
亚热带建筑科学国家重点实验室开放课题(2010KB24)
关键词
蒸汽发生器
二回路
过冷沸腾
两流体模型
数值模拟
steam generator
secondary circuit
subcooled boiling
two-fluid model
numerical simulation
