Technology Development of Estimation Method for Complex Gas-liquid Two-phase Flow in Nuclear Reactors:(Development of Void Fraction Measurement Techniques, Numerical Simulation, and Nonlinear Statistics Analysis for Unsteady, Inhomogeneous Gas-Liquid Two-

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Numerical simulation of gas-liquid two-phase flow is important for design of nuclear power systems. Conventional codes require experiments from laboratory scale to mock-up to obtain database for constitutive equations and verification. The aim of this study is to provide new simulation technique to substitute for a part of costly experiments. The extended two-fluid model developed by Hitachi, Ltd. was employed to treat inhomogeneous and intermittent two-phase flow behavior, which had been considered through constitutive equations. Validity of the new simulation code for complex two-phase flow was proved by comparison between calculated and experimental void fraction signals from two-phase flows in circular tubes, CCFL of a thick plate, and natural circulation of aerated pool in double cylinders. For measurement of instantaneous, multi-dimensional void fraction distributions, wire-mesh sensor techniques were employed for all test setups. It was found that the two-phase flow has higher orders of dynamics than initially expected, leading to development of robust analysis methods. The comparison was successful for well-structured flow patterns as slug flow, since the large diameter bubbles show low dimensional dynamics. It is also noted that an optimal delay time reconstruction method and a point correlation dimension method together were useful to increase the reliability of the analysis.
日本混相流学会の論文