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11:40
20 mins
Bubble behavior and boiling characteristics in subcooled pool nucleate boiling of a pair of heater rods simulating vertical isolation condenser (I/C) piping
Yuki Kamimura, Hideo Nagasaka, Hiroshige Kikura, Atsushi Ui, Hiromichi Miura
Session: Control of heat transfer II
Session starts: Wednesday 05 November, 11:40
Presentation starts: 11:40
Room: Lecture room A
Yuki Kamimura (Institute of Science Tokyo)
Hideo Nagasaka ()
Hiroshige Kikura (Institute of Science Tokyo)
Atsushi Ui (Central Research Institute of Electric Power Industry)
Hiromichi Miura (Central Research Institute of Electric Power Industry)
Abstract:
In recent years, research and development of new types of nuclear power plants have been intensified based on the premise of ensuring safety and strengthening safety measures. When an isolation condenser is installed in a floating nuclear power plant, there is an idea to use vertical pipes to take advantage of natural circulation. In this design, knowledge on the relationship between bundle pitch and boiling characteristics is needed. In this report, subcooled pool nucleate boiling was performed while changing the distance between a pair of vertical heater rods, and bubble behavior was investigated by measuring images of bubbles with a high-speed camera. The influence of the pitch on the boiling characteristics was also investigated by acquiring the surface superheat and boiling curves of the heater rod. As a result, it was confirmed that the effect of pitch on the heater rod surface temperature was small within the range of this test. Furthermore, from the results of the bubble image acquisition, it was confirmed that the bubble generation, detachment, and condensation processes of subcooled nucleate boiling on the heater rod surface occur in a very narrow region near the surface and do not affect the flow near the other heater rod.