3523 改良界面追跡法による燃料集合体内流体混合相関式の評価(S49-3 流動,原子炉用機器(2),S49 原子炉システムおよびその要素技術)

概要

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The Reduced-Moderation Water Reactor (RMWR) adopts a tight-lattice core with triangular fuel rod arrangement and remarkably narrow gap spacing between rods. The criteria of boiling transition (BT) is one of most important subjects for such reactor but there has been no sufficient information from previous experimental or analytical studies about the effects on the gap spacing, grid spacer shapes on the BT characteristics. Thus, we start to develop a detailed two-phase flow simulation code with interface tracking method to get information of two-phase flow in tight-lattice bundles. In this paper, the simulation code results are compared to existing experimental results of 2-channel air water mixing tests to verify code performance, and the existing two-phase flow correlation for fluid mixing is evaluated using detailed numerical simulation data.
2005-09-18