Natural circulation is a particular operating condition of nuclear power system,and reversed flow occurs in the inverted U-shaped tube bundle of the steam generator,which affects the heat transfer between the primary and secondary sides and the operation stability.In this research,In this study,the calculation code of primary flow distribution in steam generator of nuclear power unit is developed,and the accuracy of the calculation code is verified by the Finnish PACTEL pressurized water reactor experiment.The effects of loop mass flow,tube height and primary inlet temperature on the flow distribution of inverted U-tube bundle steam generator are discussed.The results show that the lower the tube height and the lower the inlet temperature of the primary side of the inverted U-shaped tube bundle,the smaller the critical pressure drop and critical flow velocity will be.Compared with the change of the height of the inverted U-shaped tube,the change of the inlet temperature of steam generator primary side affects the flow distribution of the inverted U-shaped tube bundle more significantly.The reversed flow could be suppressed by increasing the circulation mass rate,and it will disappear when the mass rate increases to a threshold.
Steam generatorNatural circulationReversed flowInverted U-shapeFlow distribution
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