The spherical harmonics (Pn) finite element method, the Sn finite element method, the triangle transmission probability method and the discrete triangle nodal method were all introduced to solve the neutron transport equation for unstructured fuel assembly respectively. The computing codes of each method were encoded and numerical results were discussed and compared. It was demonstrated that these four methods can solve neutron transport equations with unstructured-meshes very effectively and correctly, they can be used to solve unstructured fuel assembly problem.
Volume Subject Area:Reactor Physics and Transport Theory
Keywords:Neutron transport, Unstructured, Fuel assembly, Numerical calculation
Topics:Fuels, Geometry, Manufacturing, Neutrons
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