Abstract
The exact kernel method for linear transport problems with azimuth-dependent angular fluxes is here based on the evaluation of average scattering densities (ASD's) that fully describe the neutron (or particle) transfer between subsets of the unit sphere of directions by anisotropic scattering. Reciprocity and other ASD functional properties are proved and combined with the symmetry properties of suitable SN quadrature sets. This greatly reduces the number of independent ASD's to be computed and stored. An approach to perform ASD computations with reciprocity checks is presented. The ASD expressions of the scattering source for the typical 2D geometries are explicitly given.
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