This report presents a comparison between heat transfer crisis data with vertical upward flow of steam-water mixtures in round tubes, obtained with different experimental plants.nThe experimental plants CISE 1ET1-2 and 1ET1-3 and SOR1N high pressure facility are briefly described.nThe results, obtained with the same test element, are generally in good agreement, but under some conditions, still unexplained discrepancies are evident. This is in agreement with the observations made by other researchers, with both round ducts and rod bundles.nThe discrepancies are analyzed and a margin of uncertainty is derived for the critical power values.
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