Development of three-dimensional thermal-hydraulic analysis code for supercritical water-cooled reactor

超臨界圧水冷却炉のための三次元熱流動解析コードの開発

三澤 丈治; 吉田 啓之  ; 玉井 秀定; 高瀬 和之

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

JAEA is developing the two-phase flow analysis code ACE-3D to predict quantitatively thermal-hydraulic phenomena in light-water nuclear reactors from the former. Now, in order to clarify thermal-hydraulic characteristics in rod bundles of a supercritical light water reactor (SCWR), thermal property of water coded into ACE-3D was expanded to simulate the supercritical pressure condition. In consequence, the transient analysis from subcritical pressure to supercritical pressure was enabled by ACE-3D. In addition, the standard k-e turbulence model was introduced to enhance the prediction accuracy by a low-Reynolds number k-e turbulence well known as Launder-Sharma model. From the results of a series of transient and steady analyses on supercritical flow in a pipe by ACE-3D, the following considerations were derived: (1) Physical value changes between supercritical and subcritical pressure regions were smooth; (2) Predicted wall temperatures in a pipe were good agreement with those obtained by heat transfer experiment using supercritical water.