Abstract: Neutron transport calculation of PWR fuel assembly provides homogenization group constants, hence, it is deserved to research how to obtain few group homogenization parameters required by core diffusion calculation under the condition of considering neutron anisotropic scattering. Theory model of the transport correction calculation methods was derived and numerical solving process of Inflow transport correction calculation method was introduced. The corresponding code was developed in Bamboo-Lattice to verify all of the transport correction calculation methods with benchmarks. The results indicate that Inflow transport correction calculation method shows higher calculation accuracy under the premise of insuring efficiency.