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A Large-scale three-dimensional simulation on thermal-hydraulics in a fuel bundle for SCWR

SCWR用燃料集合体内熱流動に関する大規模3次元シミュレーション

三澤 丈治; 高瀬 和之; 吉田 啓之 ; 小瀬 裕男*; 岡 芳明*

Misawa, Takeharu; Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Oka, Yoshiaki*

Since the supercritical fluids have a special feature regarding thermo-physical properties of fluid density, thermal conductivity, specific heat and so on, it is difficult to predict thermal-hydraulic characteristics of the supercritical fluids by the conventional analysis methods. Therefore, in order to perform the thermal design of supercritical water reactors (SCWRs), development of a numerical analysis method which can clarify thermal-hydraulics of supercritical fluids precisely is important. Japan Atomic Energy Agency has developed a numerical analysis method which can predict the thermo-fluid properties of the supercritical fluids correctly and preform the thermal design of the SCWR. To confirm adequacy of the numerical predictions by a newly developed analysis method, a large scale simulation was carried out. This paper describes the predicted results of thermal-hydraulic characteristics in the simplified fuel bundle of the SCWR.

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