An experimental study on the effect of liquid properties on the counter-current flow limitation (CCFL) during gas/liquid counter-current two-phase flow in a 1/30 scaled-down of Pressurized Water Reactor (PWR) hot leg geometry

To promote the safety of the nuclear reactors, numerous authors have carried out investigations of gas/liquid counter-current two-phase flow in order to understand the characteristics during the inception of flooding or CCFL. The present work covers an experimental and analytical study on the effect...

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Veröffentlicht in:	Nuclear engineering and design 2022-12, Vol.399, p.112052, Article 112052
Hauptverfasser:	Astyanto, Achilleus Hermawan, Indarto, Kirkland, Karen Vierow, Deendarlianto
Format:	Artikel
Sprache:	eng
Schlagworte:	Dimensional analysis Empirical analysis Flow rates Flow velocity Froude number Gas flow Glycerol Liquid flow Multiphase flow Nuclear accidents & safety Nuclear reactors Nuclear safety Parameter modification Pressurized water reactors Reactors Surface tension Two phase flow Velocity Viscosity
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