TED-AJ03-581 EXPERIMENTAL STUDY OF THERMAL-HYDRAULIC BEHAVIOR OF COOLANT OUT OF NEUTRON REFLECTOR FOR APWR DURING REFLOODING OF LARGE BREAK LOCA

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An experimental study was carried out to investigate the steam-water two-phase flow of coolant in the Neutron Reflector (N/R) during the reflooding of large break Loss Of Coolant Accident (LOCA). The experimental apparatus simulated the geometry and the thermal capacity of one hole which modeled a typical size of N/R cooling-hole, the lower plenum, and the upper plenum. The steam and water were used as the practical working fluids. The inlet water flow rate was controlled to be constant by the injection pump. The system pressure and inlet water temperature were controlled to simulate the conditions of supposed LOCA phenomena which were estimated by the analytical code. The system pressure, temperature, and flow rate of steam. and water were measured simultaneously to study the thermal-hydraulic behaviors out of the cooling-hole. Further, the behavior of liquid lumps and droplets flow during the simulated reflooding was observed from the outlet of the test section. The closed inspection revealed that the flow condition out of the test section changed during the simulated reflooding and was classified into three stages. At the initial stage, the liquid lumps and the droplets flowed continuously like a fountain. At the medium stage, misty flow appeared, i.e. dispersed small droplets and/or liquid lumps flowed in steam flow. At the final stage, the liquid lumps flowed periodically with a little amount of steam flow. In this study, the effects of the reflooding velocity and the initial metal temperature were clarified. For the lower reflooding velocity, the ratio of steam flow rate increased. For the higher initial metal temp erature, the integration of steam and water flow rate increased.[figure]
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TED-AJ03-581 EXPERIMENTAL STUDY OF THERMAL-HYDRAULIC BEHAVIOR OF COOLANT OUT OF NEUTRON REFLECTOR FOR APWR DURING REFLOODING OF LARGE BREAK LOCA

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