期刊文献+

棒束中高含气量空泡份额计算模型适用性的研究

Applicability of Void Fraction Models in Rod Bundle at High Quality Conditions
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摘要 在子通道分析程序中,空泡份额计算模型对两相流的分析预测结果有显著影响。在较高含气率条件下,空泡份额计算模型在子通道分析程序COBRA中的适用性并没有经过充分的验证。本文用COBRA程序中自带的空泡份额计算模型与选自文献的4个空泡份额模型,对4×4棒束的气-液两相流进行子通道分析。结合实验数据,选取相对焓升和相对质量流速比,对预测结果进行分析评估。结果表明,在本文的计算范围内,Dix模型和滑速比S=1.5时的滑速比模型的预测结果最优。 Void fraction model is of great importance to the sub-channel analysis. However, the applicability of the void fraction models in the sub-channel codes COBRA under high void fraction conditions is not sufficiently validated. Based on a literature review, four void fraction models are selected and applied to the COBRA code to calculate the thermal hydraulic parameters in rod bundles. Comparing to the experimental data obtained in a 4×4 rod bundle using water as coolant, the selected void fraction models are assessed by using relative enthalpy rise and relative mass flux in various sub-channels. It was found that the calculated sub-channel parameters with the Dix model and the slip model (with a slip ratio of 1.5) give the best agreement with the experiment data.
出处 《核动力工程》 EI CAS CSCD 北大核心 2009年第6期24-27,37,共5页 Nuclear Power Engineering
基金 973计划项目(No.2007CB209804)资助
关键词 空泡份额 燃料棒束 高含气率 模型评估 Void fraction, Fuel bundle, High quality, Model evaluation
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参考文献4

  • 1Dae-Hyun Hwang, Kyong-Won Seo, Hyuk Kwon. Analysis on the NUPEC BFBT Benchmark Exercises Using the Subcharmel Code MATRA[C]. The 12^TM International Topical Meeting on Nuclear Reator Thermal Hydraulics, U. S. A., 2007.
  • 2Meikamu A. Woldesemayat, Afshin J. Ghajar. Comparison of Void Fraction Correlations for Different Flow Patterns in Horizontal and Upward Inclined Pipes[J]. International Journal of Multiphase Flow, 2007, 33:347-370.
  • 3Herkenrath H, Hufschmidt W, Jung U, et al. Experimental Investigation of the Enthalpy and Mass-Flow Distribution in 16-Rod Clusters with BWR+PWR Geomentries and Conditions[J]. Nuclear science and technology, 1981.
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