Neutron transport studies in fast reactor shields

The present study aims at evaluating the relative accuracies with which the different approximations to the transport theory represent the spatial and spectral distribution of neutrons in a typical fast reactor shield. Diffusion, removal diffusion and discrete ordinate transport calculations, with and without the inclusion of anisotropic scattering effects, have been performed for the lateral and axial shield configurations of the French fast reactor Rapsodie. The results have been compared, with the measurements made in Rapsodie and the NIOBE calculations made earlier