Abstract
A generalization of the Response Matrix spectral nodal method is applied to fixed–source discrete ordinates (SN ) radiative transfer and neutron transport problems in slab geometry. This method is extended to forward and adjoint energy multigroup problems with anisotropic scattering including the upscattering events. We present the numerical methodology which generates SN solutions absolutely free from spatial truncation errors. To discuss the efficiency of the method, we offer a number of numerical results for two typical test problems.
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