BENSON – High pressure thermal hydraulic separate effect tests
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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Equipment and components testing
Framatome has the largest panel of testing facilities and technical centers worldwide in nuclear industryView 31 Products.
Fuel and core analyses, calculations, codes
Benefit from our advanced nuclear methods for fuel assembly design, core design, safety analysis and core monitoringView 26 Products.