The solution of the neutron diffusion equation in 2D polar coordinates is a crucial aspect of nuclear reactor design. The nodal methods are significantly more accurate than traditional methods such as finite difference method (FDM) and finite element method (FEM). However, these methods can be used only on specific geometries. This research activity aims to develop a novel approach for solving the neutron diffusion equation in 2D polar coordinates, which can be applied to various geometries. The proposed method will be compared with existing methods to evaluate its accuracy and efficiency. The results will be used to optimize the design of nuclear reactors and improve their safety and performance.