Reference No: A1572

Test facility: KATHY – BENSON Multifunction Thermo-hydraulic Testing Loop

Flow nucleate boiling is characterized by a high heat transfer. It is of relevance for the design of heat exchangers, boilers and nuclear fuel assemblies. Nevertheless, the heat transfer is limited by a corresponding maximum heat flux at the beginning of a boiling crisis or transition which is called critical heat flux (CHF). Framatome's testing facility of Heat Transfer Performance and Critical Heat Flux at water, steam and two-phase flow conditions eliminates modelling uncertainties and ensures safety margins.

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