Iterative Solution of the Neutron Transport Equation by Means of Diffusion Techniques

In the framework of the solution of the transport equation by means of diffusion techniques, an iterative procedure is presented that permits us to calculate the point-dependent diffusion coefficient, D_k(k = x,y,z), using standard diffusion codes. Numerical comparisons show that this procedure attains a flux distribution much closer to the transport distribution after one iteration than the classical diffusion flux. The time of the calculation is about twice that required by classical diffusion.