| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 296517 | Nuclear Engineering and Design | 2014 | 9 Pages |
•Flooding experiments were conducted using steam and water in a large-diameter tube.•The effects of water subcooling were studied during the experiment.•Tests were conducted at a variety of water flow rates and temperatures.•The data confirmed use of a correlation to account for water subcooling.
A counter current annular flow experiment was performed to determine flooding conditions for varying degrees of subcooling using steam and water. The findings can be used in reactor safety codes to provide an improved model of flooding during accident analysis. The test section is a stainless steel tube which is approximately a 5/16 scale version of a pressurized water reactor (PWR) surge line. The water flows in an annular film down the inside of the tube and steam flows upward through the annulus. Flooding is the point at which the water film reverses direction and begins to travel upward. Flooding tests were conducted at atmospheric pressure for water flow rates between 0.0132 m3/min and 0.0416 m3/min and water inlet temperatures between 308 K and 370 K. The data obtained at high water subcooling indicate a significant departure from accepted flooding correlations developed for air–water systems which is expected because vapor condensation alters the steam inlet flow rate needed to induce flooding. The data more closely follow air–water data at low subcooling. Such data has not been seen in the literature for steam–water flooding experiments in a large diameter vertical tube and will serve as an important benchmark.
