Article ID Journal Published Year Pages File Type
8070356 Annals of Nuclear Energy 2013 18 Pages PDF
Abstract
► A multigroup neutron transport An code (BERM-AN) is presented. ► A rigorous treatment of the linearly anisotropic scattering is taken into account. ► A response matrix solution procedure coupled to the boundary element method is used. ► Numerical results show that the BERM-AN code is accurate, efficient and robust.
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Physical Sciences and Engineering Energy Energy Engineering and Power Technology
Preview
Solution of 3D multigroup, linearly anisotropic scattering, criticality problems by the AN boundary-element response-matrix method
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