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.
3.1.1 Experiment for two-phase flow in the heat transfer tube of FBR
3.2.2 Experimantal estimation for the Effect of Axial Power Distribution on Critical Power
3.4.1 Analysis for phenomena of Fukushima accident
3.4.2 Deformation and phase transition of the structure materials in the nuclear reactor
3.4.3 Analysis of migration behavior of melting debris in the nuclear reactor
3.4.4 Jet break behavior of melting materials
3.4.5 Analysis of detailed temperature distribution in the nuclear reactor
3.4.6 Experiment for heat flow in the debris
3.4.7 Experiment for heat transfer of seawater
3.4.8 Test measurement of void fraction distribution in fuel assembly