Abstract: A nodal Green's function method for cylindrical geometry for multidimensional neutron diffusion calculation is developed.First,the neutron diffusion equation is converted to three coupled one-dimensional partial flux equation through transverse integration.For the radial partial flux equation,the differential term is decomposed to a diffusion term plus a modified term,which is called modified source.Therefore,the three equations show the same form as for slab geometry.Second,by way of the second kind boundary condition Green's function for slab geometry,the three equations are integrated to obtain the integral equations.For the modified source term,it can be converted to Green's function's differentiation term through partial integration.At last,the equations are solved by source iteration method.Through benchmark computation,this method shows high speed and high extent of accuracy.It is a effective method for reactor design of three dimensional cylindrical geometry and for nuclear fuel management calculation.