Numerical Analysis of Heat Transfer Test of Supercritical Water in a Tube Using the Three-Dimensional Two-Fluid Model Code
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概要
- 論文の詳細を見る
The three-dimensional two-fluid model analysis code ACE-3D is developed in Japan Atomic Energy Agency for the thermal design procedure on two-phase flow thermal-hydraulics of light water-cooled reactors. In order to perform thermal hydraulic analysis of SCWR, ACE-3D is enhanced to supercritical pressure region. As a result, it is confirmed that transient change in subcritical and supercritical pressure region can be simulated smoothly using ACE-3D, that ACE-3D can predict the results of the past heat transfer experiment in the supercritical pressure condition, and that introduction of thermal conductivity effect of the wall restrains fluctuation of wall temperature.
- 一般社団法人 日本機械学会の論文
著者
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Tamai Hidesada
Japan Atomic Energy Agency
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Takase Kazuyuki
Japan Atomic Energy Agency Nuclear Science And Engineering Directorate
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Yoshida Hiroyuki
Japan Atomic Energy Agency
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MISAWA Takeharu
Japan Atomic Energy Agency
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