The fuel assemblies bow with different stresses in the PWR reactor core and this phenomenon can significantly affect the local neutron moderation in the reactor core. Based on the CGN’s in-house software package PCM, which is composed of the fuel assembly neutron cross section software PINE and the core design software COCO, this study developed a specific model for fuel assembly bowing to analyze the impact on local power distribution, and compared the results with that of the Monto Carlo code JMCT. The study shows that the results of fuel assembly bowing model in PCM have good consistency with those of JMCT, and that PCM is valid in fuel assembly bowing analysis. The fuel assembly bowing has a significant impact on core local power distribution. This phenomenon shall be specially considered in the PWR reactor design.