Neutron transport problems in anisotropic media

In nuclear reactor physics, neutron transport in media having anisotropic properties is of interest in modelling largely voided configurations, such as boiling-water and gas-cooled reactors. In order to treat such problems, neutronic methods need to be extended and adapted. The present work is devoted to the solution of transport problems for materials in which cross-sections are dependent on the direction of motion of the neutrons. A simple one-dimensional plane configuration is assumed, in order to be able to obtain analytical solutions and to gain physical insight into the transport phenomenon. Results can thus be considered as benchmarks for numerical algorithms employed in realistic cases.