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Super fast reactor R&D projects in Japan, 4; Numerical estimation of thermal-hydraulic characteristics of supercritical fluids in tight-lattice bundles by three-dimensional two-fluid model analysis code ACE-3D

日本におけるスーパー高速炉の研究開発プロジェクト,4; 三次元二流体モデル解析コードACE-3Dによる稠密格子バンドル内の超臨界圧流体伝熱流動特性の数値解析

中塚 亨; 三澤 丈治; 吉田 啓之; 高瀬 和之

Nakatsuka, Toru; Misawa, Takeharu; Yoshida, Hiroyuki; Takase, Kazuyuki

超臨界圧水冷却炉の伝熱流動特性を解析するために、原子力機構では軽水炉の二相流解析用に開発した三次元二流体モデルコードACE-3Dの改良を行っている。超臨界圧流体を用いた伝熱試験結果をもとに改良したACE-3Dを使って、超臨界圧領域での予測性能を評価した。その結果、表面温度の予測値は測定値と一致することを確認した。超臨界圧軽水冷却高速炉(スーパー高速炉)の稠密格子燃料バンドルの伝熱流動特性を評価するため、改良ACE-3Dを使って19本バンドルで簡易模擬した燃料集合体を解析した。その結果、被覆管表面最高温度628$$^{circ}$$Cは中心燃料棒の出口近傍で生じ、燃料と被覆管の健全性を評価する判断基準である被覆管表面最高温度650$$^{circ}$$C以下を満たすことがわかった。

To analyze thermal hydraulics in the core of supercritical-water-cooled reactors, JAEA has been improved a three-dimensional two-fluid model analysis code ACE-3D, which has been developed originally for two-phase flow of LWRs. Heat transfer experiments of supercritical fluids flowing in a tube, a vertical annular channel around a heater pin and 7-rod bundles were analyzed with the improved ACE-3D to assess the prediction performance of the code at supercritical region. As a result, it was confirmed that the calculated wall surface temperatures agreed with the measured results. To evaluate thermal hydraulic characteristics of a tight-lattice fuel bundle of Super Fast Reactor, a simplified 19-rod fuel assembly was analyzed. Maximum clad surface temperature was observed at the position facing to the narrowest gap on the center rod near the outlet and the value was 901K. The predicted MCST satisfies thermal design criteria to ensure fuel and cladding integrity.

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