TED-AJ03-415 HEAT TRANSFER TO A SUPERCRITICAL PRESSURE FLUID FLOWING UPWARD IN A VERTICAL TUBE OF SMALL DIAMETER
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概要
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Recently attention to the heat transfer to supercritical pressure fluids has been attracted again, in relation to the development of a Supercritical pressure water Cooled Power Reactor (SCPR). The heat transfer to supercritical pressure fluids is characterized by a strong dependence of the variation of fluid physical properties on temperature. Based on a large number of experimental data for water and carbon dioxide, it has been clarified that the specific features of the heat transfer to supercritical pressure fluids flowing in tubes are a 'normal' heat transfer at a low heat flux and a 'deteriorated' heat transfer at a high heat flux. In the 'normal' heat transfer, the heat transfer coefficient has a peak when the bulk fluid temperature is slightly below the pseudocritical temperature, although the peak becomes lower as the heat flux increases. For the 'normal' heat transfer, various correlation equations have been developed based on experimental data for water and/or carbon dioxide. In the SCPR, a tightened fuel rod pitch will be adopted. There are, however, only a few experimental data on the heat transfer to supercritical pressure fluids in tubes of such a small hydraulic diameter. In the present study, experimental data were obtained on the heat transfer to supercritical pressure fluid flowing upward in a uniformly heated smooth tube having a small inside diameter of 4.4 mm, using HCFC22 as the test fluid. As illustrated in Figure A-1,the measured heat transfer coefficients showed the characteristics qualitatively similar to those for the tubes of larger diameter : the 'normal' heat transfer at the low heat flux and the 'deteriorated' heat transfer at the high heat flux. The predicting performance of correlation equations developed so far for the 'normal' heat transfer was tested using the present data, in addition to the data for water and carbon dioxide by several researchers. As shown in Figure A-2,it was found that the Watts and Chou correlation equation is the most applicable to the small diameter tube. [figure]
- 一般社団法人日本機械学会の論文
著者
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Mori Hideo
Dept. of Electronic-Mechanical Engineering, Nagoya University
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NISHIDA Koji
Hitachi, Ltd.
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Ohno Masaki
Dept. Of Mechanical Engineering Science Kyushu Univ.
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Yoshida Suguru
Dept. Of Mechanical Engineering Science Kyushu Univ.
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Yoshida S
Dept.of Mechanical Science And Eng. Graduate School Of Eng. Kyushu Univ.
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YAMASHITA Tohru
Dept. of Mechanical Engineering Science, Kyushu Univ.
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KOMITA Hideo
Toshiba Corp.
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Yamashita Tohru
Dept. Of Mechanical Engineering Science Kyushu Univ.
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Mori H
Dept.of Mechanical Science And Eng. Graduate School Of Eng. Kyushu Univ.
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Mori Hideo
Dept. Of Mechanical Engineering Science Kyushu Univ.
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Mori Hideo
Department Of Applied Physics Faculty Of Engineering University Of Tokyo:industrial Cathode Ray Tube
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Nishida Koji
Hitachi Ltd.
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