823 超臨界二酸化炭素の流速分布計測(動力エネルギーの基盤技術I)(OS.9 動力エネルギーの基盤技術 : 動力エネルギーシステム部門企画)

概要

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Because supercritical water has been proposed as a coolant for the new nuclear reactor, the thermal hydraulics of high-pressure fluid in supercritical condition should be verified. In this research, the experiment for the forced convection of the supercritical fluid has been performed to investigate the heat transfer and fluid dynamics. This experiment includes the temperature measurement by thermocouples and flow, visualization by laser interferometry for thermal hydraulic analysis. CO_2 has been used as test fluid for this critical point of 31℃ and 7.4 MPa. Experiment has been completed around 40℃ and 9 MPa for the upward flow in rectangular channel heated by an one-side wall heater. Thermocouples have measured the local heat flux and the fluid temperature. For the flow visualization method, Schlieren interferometry has been applied to obtain the density distribution. A laser beam has been illuminated to pass through the window for showing the distribution of the light intensity which is proportional to the density gradient of the fluid. These images has been captured by the high-speed camera with the time interval of 1/1000 second. Then, the cross-correlation method has been applied for these images to estimate the displacement of the density waves. From these displacement of the image, the velocity field could be calculated.
社団法人日本機械学会の論文
2001-03-09