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ISSN Online: 2377-424X
ISBN Print: 978-1-56700-474-8
ISBN Online: 978-1-56700-473-1
International Heat Transfer Conference 16
PRESSURE DROP AND HEAT TRANSFER MEASUREMENTS OF THE ONCE THROUGH STEAM GENERATOR HELICAL TUBE BUNDLES OF HIGH TEMPERATURE GAS-COOLED REACTORS
Abstrakt
Helical tube bundle is always adopted in the steam generator of nuclear reactors. The flow friction and laminar-turbulent transition in helical tubes is different from that in straight circular tubes due to the secondary flow in the cross section induced by centrifugal forces. The pressure drop in helical tubes with 5 helical diameters are measured using water and compressed air as working fluids. The Reynolds number range is 3000-400000. The flow regime includes both laminar and turbulent flow regions. The laminar-turbulent transition Reynolds number with different helical diameters was investigated. The previous correlation was compared with the
present results. The pressure drop and heat transfer coefficient of cross flow over the helical tube bundles are also measured using high pressure helium as working fluids. The Reynolds numbers are in the range of 18000-34000. The measured friction factors and Nusselt numbers were compared with existing correlations for straight tube bundles. The results showed that the existing correlations is not conservative for predicting the friction factor and Nusselt number of a helical tube bundle even the correction factor due to the attack angle is considered. New correlations of the friction factor and Nusselt number for the present helical tube bundle are proposed.
SCHLÜSSELWÖRTER:
Nuclear energy, Convection, helical tube, helical tube bundle, friction factor, heat transfer coefficient, correlation