Neutron flux distributions in media separated by a cylindrical boundary

Abstract

Expressions are derived for the neutron flux distribution due to a point source on the axis of cylindrical symmetry of two coaxial media of different properties. The two-group approximation is used, and the transfer of neutrons between the two media is represented by the introduction of fictitious neutron source distributions over the boundary. Expressions are given for the fast and slow-neutron flux distributions in both media.