Measurement of Subcooled Boiling Flow Characteristics in a Large Slab

A subcooled boiling phenomenon is an important safety concern in the downcomer of a nuclear reactor during a transient phase of a postulated accident. An experimental program has been performed to identify and quantify the phenomenon with a newly constructed test facility, 'DOBO', which has slab geometry of a test section. This study's purpose is to generate experimental data in order to develop and validate a two-phase analysis code. Unlike the previous test, the water is supplied from the bottom of the test section in order to get clearer boundary conditions. The measured data can be divided into two categories: (I) global two phase parameters such as pressure, temperature, flow rate, and water level, and (II) local two-phase parameters such as a void fraction and liquid/steam velocities