On the calculation of neutron sources generating steady prescribed power distributions in subcritical systems using multigroup X,Y-geometry discrete ordinates models

In this paper a methodology is described to estimate multigroup neutron source distributions which must be added into subcritical system drive it steady state prescribed power distribution. This work has been motivated by the principle of operation ADS (Accelerator Driven System) reactors, have cores stabilized action external sources. We use energy two-dimensional transport equation in discrete ordinates formulation (SN) and adjoint it, whose solution interpreted here as distribution measuring importance angular flux neutrons linear functional. These equations are correlated through reciprocity relation, leading relationship between interior sources produced unit length height domain. A coarse-mesh numerical method spectral nodal class, referred response matrix constant-nodal method, applied numerically solve SN equations. Numerical experiments performed analyze accuracy present so illustrate its potential practical applications.