ANNALS OF NUCLEAR ENERGY, vol.20, no.7, pp.503-518, 1993 (SCI-Expanded)
In this study, we concentrated on the solution of criticality eigenvalue problems arising from the boundary element discretization of the neutron diffusion equation. For the solution of the criticality eigenvalue problem, both the fission source iteration, and a technique based on a Neumann series expansion are utilized. The relative merits of both approaches are assessed.