Evaluation of higher K-eigenvalues of the neutron transport equation by Sn-method

Many semi-analytical methods are being developed to evaluate higher eigenvalues of monoenergetic neutron transport equation. Here, a numerical approach is presented where the well-known Snmethod is used to generate higher K-eigenvalues of neutron transport equation via the generation of a fission matrix. Although less accurate than the semi-analytical methods, the inclusion of spatial inhomogeneities, scattering anisotropies and even more energy groups would be straightforward in this method owing to the versatility of the S,-codes. It is also shown that the K-eigenvalues are always real in the mono-energetic case even if scattering is anisotropic. The inadequacy of the S,-method to reproduce the flux-source reciprocity relation in spherical geometry, noticed during the course of this work, is also briefly discussed