Spectral deterministic method applied to one-dimensional global calculation in nuclear reactors using the multigroup transport theory using the discrete ordinates formulation

Some interesting global calculations in nuclear reactors, e.g. the power generated, the ective neutron multiplication factor, the burn-up of nuclear fuel etc, are analyzed using computational simulations. The development of these models, which seek to describe these problems with great precision, are justied due to the importance of nuclear reactors as an energy option to the use of fossil fuels that contribute to global warming. In this paper, we present a Spectral Deterministic Method { eigenvalue multiplying (SDM{eigenvalue) to obtain the power distribution and the ective multiplication factor (k_eff ) in stationary, one-dimensional multigroup neutron transport problems with isotropic scattering using the discrete ordinates formulation. Two coarse-mesh methods, the spectral diamond - spectral Green's function (SD{SGF) and the Spectral Deterministic Method are implemented to solve the typical model problems. The traditional fine-mesh Diamond Difference (DD) method is used for the comparison and verication of numerical results accuracy. (author)