During operation of the nuclear power plant, fuel rods tend to bend. In order to accurately predict the thermal-hydraulic phenomena in the rod bundles with bowing rod, the profile of local parameters in two-phase flow is greatly important. In this study, experiments were conducted in 5 × 5 rod bundle channel with a bowing rod. Four different bow deformation ratios (0%, 50%, 80% and 100%) were adopted for the bowing rod. Measurements were performed using a four-sensor conductivity probe to assess local parameters in two-phase flow, including interfacial area concentration (IAC), bubble chord length, void fraction and bubble velocity. The results indicate that, after passing through the bowing section, the void fraction changes from a wall-peak distribution to a core-peak distribution. The distribution of the local parameters at L/D = 78.6 and L/D = 102.1 are almost identical, suggesting that the dissipation length of the bowing section is greater than 23.5 (102.1–78.6) L/D. The void fraction reaches highest in the center of the subchannel with a bowing rod and increases with an increase in bow deformation ratio. In the bowing rod bundle channel, both of the void fraction and bubble chord length increase with the increase of gas velocity, especially in the region of the inner subchannel. Finally, based on the measured local parameters such as bubble velocity and void fraction, a new distribution parameter model in the subchannel with a rod bow deformation ratio of 80% was proposed.