S0803-3-2 ABWR下部プレナム内流れにおける乱流場計測と乱流モデルの適用性評価(原子力発電システムおよび要素技術(3))

概要

論文の詳細を見る
The evaluation of coolant flow at a lower plenum of an advanced boiling water reactor (ABWR) is very important because there are a lot of structures such as control rod guide tubes. The simulation results by a CFD (Computational Fluid Dynamics) code can predict such complicated flow in the lower plenum. It is required to establish the database of flow structure in lower plenum of ABWR experimentally for the benchmark of CFD code. In the model of the lower plenum, we measured velocity profiles by LDV and PIV with a high-speed video camera. Velocity and turbulent energy profile are obtained from experiment and numerical simulation. Average velocity profiles were qualitatively good agreement in both experiment and simulation.
社団法人日本機械学会の論文
2009-09-12