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Research contents

1 Development of the new thermal design method

The most common approach to classify the flow, which can be found in various reactors, is to divide into 'single phase flow' and 'multi phase flow'. Water flow without boiling, or air flow is typical example of single phase flow. In thermal design of nuclear reactor, it is often the case that 'gas-liquid two phase flow' or single phase flow is treated. Therefore, the focus of our study is on development of the simulation code, which can treat these two kinds of flow.

1.1 Development of two-phase flow analysis using the phase-field interface-tracking method

1.1.1 Liquid film flow, bubble flow, spray flow

1.1.2 Phase transition model

1.1.3 Bubble flow behavior in the nuclear reactor during an earthquake

1.2 Development of two-phase flow analysis in the nuclear reactor using a three-dimensional two-fluid model

1.2.1 Bundle system analysis

1.2.2 Coupled thermo-mechanical finite-element analysis

1.3 Development of supercritical fluid heat transfer analysis method

1.4 Development of multiphase flow analysis

1.5 Development of systems analysis techniques in the nuclear reactor