Diffusion of Neutrons

This lecture covers the solutions of the diffusion of neutrons, including the review of the Diffusion Equation, analytical solutions for simple cases, and the physical significance of the diffusion area in a multiplying media. The instructor explains the one-group diffusion equation, Laplacian in different geometries, boundary conditions, and the diffusion length and area. The lecture also delves into Fick's law, the diffusion equation as a simplified version of the transport equation, and the neutron balance equation. Analytical solutions for infinite planar and point sources in an infinite medium are discussed, along with distributed sources in a finite medium. The physical significance of the diffusion area and typical values of diffusion coefficient and diffusion length for different reactor materials are also presented.