A strategy is proposed for the application of space-angle synthesis (SAS) to the finding of solutions for practical nuclear reactor neutron transport problems. A simple SAS approximation is derived. Trial functions for the approximations are to be created for each mesh point used in describing a set of similar problems which are to be solved. The strategy is concerned with constructing problems that are simpler than, but representative of, the set of problems finally to be solved. It is from transport solutions of these representative problems that the SAS trial functions are to be formed. This strategy and the simple SAS approximation are applied successfully to several sets of similar problems for which diffusion theory is inadequate.