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Numerical analysis of heat transfer test of supercritical water in a tube using the three-dimensional two-fluid model code

三次元二流体モデル解析コードを用いた超臨界圧水熱伝達実験解析

三澤 丈治; 吉田 啓之; 玉井 秀定; 高瀬 和之

Misawa, Takeharu; Yoshida, Hiroyuki; Tamai, Hidesada; Takase, Kazuyuki

In Japan, development of a supercritical water-cooled nuclear reactor (SCWR) is carried out as one of the next generation nuclear energy systems as proposed by GIF (Generation IV International Forum). In transient operation including start-up, shut-down, and accident, it is possible that coolant in a reactor changes over between supercritical pressure region and subcritical pressure region. In JAEA, three-dimensional two-fluid model analysis code ACE-3D has been developed, and has achievement of detailed thermal-hydraulic analysis code of supercritical light water reactor including transient phenomena, by enhancement of ACE-3D code to supercritical pressure region. This paper shows development and assessment of ACE-3D. It was confirmed that transient change between supercritical and subcritical pressure region can be simulated using ACE-3D, that ACE-3D can predict the results of the past heat transfer experiment in supercritical pressure region, and that introduction of thermal conductivity effect of the wall restrains temperature fluctuation on the wall.

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