Analysis of two-phase flow phenomena with FLUENT-4 code in the experiments for advanced light water reactor safety

Jaakko Miettinen,Mika P Tuomainen,Ismo Karppinen, J Tuunanen

mag(2002)

Cited 24|Views3
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Key words
pressure vessel,momentum transfer,critical heat flux,volume fraction,void fraction,natural convection,two phase flow,fiber optic,reactor pressure vessel,nuclear reactor
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