Journal of South China University of Technology (Natural Science Edition) ›› 2013, Vol. 41 ›› Issue (5): 87-92.doi: 10.3969/j.issn.1000-565X.2013.05.014

• Power & Electrical Engineering • Previous Articles     Next Articles

Numerical Simulation of Subcooled Boiling in Secondary Circuit of Steam Generator

Zhang Xiao-ying Ding Fei Chen Jia-yue   

  1. School of Electric Power,South China University of Technology,Guangzhou 510640,Guangdong,China
  • Received:2012-05-18 Revised:2013-01-21 Online:2013-05-25 Published:2013-04-01
  • Contact: 张小英(1973-)，女，教授，主要从事核电安全技术与理论研究． E-mail:zxy1119@scut.edu.cn
  • About author:张小英(1973-)，女，教授，主要从事核电安全技术与理论研究．
  • Supported by:

    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)

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Abstract:

In order to deeply investigate the vapor-liquid two-phase boiling heat transfer and flow characteristics inthe secondary circuit of steam generator,the wall heat flux partition in the subcooled boiling region was divided byusing the RPI model for revising the two-fluid model of the CFD ( Computational Fluid Dynamics) program,andsome published experimental results were used to validate the reliability of the revised mode.Moreover,a casestudy 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 allobtained.

Key words: steam generator, secondary circuit, subcooled boiling, two-fluid model, numerical simulation

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