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倾斜限制空间内池式沸腾临界热流密度分析模型研究

An Analytical Model for Pool Boiling Critical Heat Flux in Inclined Confined Spaces

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【作者】 文青龙陈军赵华

【Author】 WEN Qing-long1,2,CHEN Jun2,ZHAO Hua2 (1.School of Nuclear Science and Engineering,Shanghai Jiao Tong University,Shanghai,200240,China; 2. Key Laboratory of Bubble Physics and Natural Circulation,Nuclear Power Institute of China,Chengdu,610041,China.)

【机构】 上海交通大学核科学与工程学院中国核动力研究设计院空泡物理和自然循环国家级重点实验室

【摘要】 在对汽泡行为进行分析的基础上,以分离流模型、稳定性分析、表面能守恒为理论基础,从界面脱离机理出发,建立了临界热流密度分析模型。采用该模型对文献[1]实验工况进行计算,计算结果与5mm和8mm窄缝尺寸实验数据在定性和定量上都符合得较好;计算结果虽在定性上反映了3mm窄缝尺寸实验数据的变化趋势,但定量上却与实验数据存在一定的偏差。采用该模型对其他文献实验工况进行计算,其结果与Yang、Kim、Howard和Gribov的实验数据吻合较好,而与Guo关联式存在一定的偏差。

【Abstract】 Based on the bubble behaviors observed during experiments of pool boiling critical heat flux in inclined confined spaces,an analytical model of critical heat flux is presented,including four major sub-models:a separated flow model,a stability analysis,a heater surface energy balance and a lift-off criterion. Calculation results of critical heat flux agree well with experiment results of 5mm and 8mm gap sizes both qualitatively and quantitatively. Though calculation results show the varying trend of experiment results of 3 mm gap size qualitatively,to some extent the discrepancies do exist quantitatively. In addition,the calculation results predict well the experimental results of Yang,Kim,Howard and Gribov ,but the discrepancies between the calculation results and Guo’s correlation are great.

  • 【文献出处】 核动力工程 ,Nuclear Power Engineering , 编辑部邮箱 ,2010年S1期
  • 【分类号】TL333
  • 【被引频次】4
  • 【下载频次】158
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