[en] Two-phase flow simulation has been an extended research topic over the years due to the importance of predicting with accuracy the flow behavior within different installations, including nuclear power plants. Some of them are low pressure events, like low water pressure injection, nuclear refueling or natural circulation. This work is devoted to investigate the level of accuracy of the results when a two-phase flow experiment, which has been carried out at low pressure, is performed in a one-dimensional simulation code. In particular, the codes that have been selected to represent the experiment are the best-estimate system codes RELAP5/MOD3 and TRACE v5.0 patch4. The experiment consists in a long vertical pipe along which an air-water fluid in bubbly regime moves upwards in adiabatic conditions and atmospheric pressure. The simulations have been first performed in both codes with their original correlations, which are based on the drift flux model for the case of bubbly regime in vertical pipes. Then, a different implementation for the drag force has been undertaken, in order to perform a simulation with equivalent bubble diameter to the experiment. Results show that the calculation obtained from the codes are within the ranges of validity of the experiment with some discrepancies, which leads to the conclusion that the use of a drag correlation approach is more realistic than drift flux model. (author)