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核聚变与等离子体物理 ›› 2019, Vol. 39 ›› Issue (3): 265-269.DOI: 10.16568/j.0254-6086.201903012

• 核聚变工程技术 • 上一篇    下一篇

聚变堆偏滤器过冷水流动沸腾强化换热性能研究

刘 萍,王彭通,丁文龙,罗晨珲   

  1. (安徽理工大学机械工程学院,淮南 232001)
  • 出版日期:2019-09-15 发布日期:2019-09-16
  • 作者简介:刘萍(1978-),女,江苏盐城人,博士,教授,硕士生导师,主要从事过冷沸腾、气液两相流等的研究。
  • 基金资助:

    国家自然科学基金(11805005);国家磁约束核聚变能发展研究专项(2014GB101001,2014GB110000)

Enhanced heat transfer performances of subcooled water flow boiling in fusion reactor divertor

LIU Ping, WANG Peng-tong, DING Wen-long, LUO Chen-hui   

  1. (College of Mechanical Engineering, Anhui University of Science and Technology, Huainan 232001)
  • Online:2019-09-15 Published:2019-09-16

摘要:

选择欧拉多相流模型和非平衡沸腾模型,用Fluent 软件对单边受热竖直向上平滑管进行了过冷流动沸腾换热的数值分析。研究了不同质量流速、进口温度和热流密度对对流换热系数和空泡份额的影响,并分析了它们对传热恶化的影响。

关键词: 过冷流动沸腾, 单边受热, 对流换热系数, 空泡份额

Abstract:

By using Fluent software with the Eulerian multiphase model and Non-equilibrium boiling model, the subcooled flow boiling heat transfers was numerically simulated in the plain upward vertical tubes under the condition of one-side heating. The influences of the different mass flux, inlet temperatures and heat flux on the heat transfer coefficient, the void fraction and heat transfer deterioration were investigated.

Key words: Subcooled flow boiling, One-side heating, Heat transfer coefficient, Void fraction

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