Journal of Nuclear Science and Technology · 1982 · 93 citations · 7 references
EngineeringCoiled TubeSingle-phase FlowFluid MechanicsMechanical EngineeringHeat PipeGas-liquid FlowTwo-phase FlowHeat Transfer ProcessHeat Transfer CoefficientTransport PhenomenaThermodynamicsFriction Pressure DropHeat TransferMultiphase FlowCoiled TubesFluid MachineryHeat ExchangerHeat Transfer EnhancementThermal Engineering
A model test rig of an integrated type marine water reactor was used to investigate two‑phase friction pressure drop and heat transfer coefficients in a once‑through steam generator with helically coiled tubes, employing tube dimensions and thermal‑fluid conditions that match real reactors to obtain directly applicable data. Experimental results showed that modified Kozeki’s prediction best matched the friction pressure drop data, modified Martinelli‑Nelson agreed within 30 %, coiled‑tube heat transfer coefficients were similar to straight‑tube predictions, Schrock‑Grossman correlation agreed well below 3.5 MPa, and dryout is expected at a quality greater than 90 % under the studied conditions.
Two-phase friction pressure drop and heat transfer coefficients in a once-through steam generator with helically coiled tubes were investigated with the model test rig of an integrated type marine water reactor. As the dimensions of the heat transfer tubes and the thermal-fluid conditions are almost the same as those of real reactors, the data applicable directly to the real reactor design were obtained. As to the friction pressure drop, modified Kozeki's prediction which is based on the experimental data by Kozeki for coiled tubes, agreed the best with the experimental data. Modified Martinelli-Nelson's prediction which is based on Martinelli-Nelson's multiplier using Ito's equation for single-phase flow in coiled tube, agreed within 30%. The effect of coiled tube on the average heat transfer coefficients at boiling region were small, and the predictions for straight tube could also be applied to coiled tube. Schrock-Grossman's correlation agreed well with the experimental data at the pressures of lower than 3.5 MPa. It was suggested that dryout should be occurred at the quality of greater than 90% within the conditions of this report.
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Friction Factors for Turbulent Flow in Curved Pipes
H. Itō · Journal of Basic Engineering · 1959 · 641 citations
Forced Convection Boiling in Tubes
V.E. Schrock, Lawrence M. Grossman · Nuclear Science and Engineering · 1962 · 139 citations