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Advanced Course in Heat Transfer in Nuclear Reactor Safety
September, 1-5, 1980, Dubrovnik, Yugoslavia

DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf


ISBN Print: 978-0-89116-223-0

1.11 Two Phase Flow Liquid Metal Boiling Characteristics

pages 259-286
DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf.120
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RESUMO

Theoretical and experimental studies on steady state sodium two phase flow regimes will be presented.
From the experimental results two phase flow frictional pressure drop correlations were derived for the range of vapour quality of up to 15% which corresponds to a void fraction of 95%. Stationary boiling experiments were conducted in tubular and annular geometry varying the heat flux and mass flow rate according to the vapour quality chosen as experimental variable. A comparison of the experimental results with the "frictional multiplier" correlations proposed by other authors is done. A least square fit correlation of the measured data covering the Lockhart Martinelli parameter in the range of 7. 10−2 < XLM< 30 is proposed and comparison with measurements from other laboratories is done.
This work was performed in collaboration with the CENG-Grenoble Centre of the CEA France. The CENG Grenoble Center made available the annular test section.

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