The system of finite-difference equations which couple the neutron flux values at discrete points in phase space vas cast into the general eigenvalue problem for a steady-state condition. The feasibility of direct iteration toward a specified steady-state condition, "direct search," was demonstrated by computer calculations. A study was made of the equations and iterative behavior of calculations for the directed neutron flux in one-dimensional slab geometry with anisotropic scattering and multi-group treatment of the energy variable. Calculations were also performed using Carlson's Sn equations. Several problems encountered in analysis of a variety of nuclear reactor cares were solved by application of the direct search techniques to the formulation associated with the diffusion approximation to neutron transport.
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