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Listar por palabra clave "Moving mesh scheme"

Mostrando ítems 1-2 de 2

Approximation of The Neutron Diffusion Equation on Hexagonal Geometries Using a h-p finite element method

Fayez Moustafa Moawad, Ragab (Universitat Politècnica de València, 2016-06-07)

[EN] The neutron diffusion equation is an approximation of the neutron transport equation that describes the neutron population in a nuclear reactor core. In particular, we will consider here VVER-type reactors which use ...
Moving meshes to solve the time-dependent neutron diffusion equation in hexagonal geometry

Vidal-Ferràndiz, Antoni; Fayez Moustafa Moawad, Ragab; Ginestar Peiro, Damián; Verdú Martín, Gumersindo Jesús (Elsevier, 2016-01)

To simulate the behaviour of a nuclear power reactor it is necessary to be able to integrate the time-dependent neutron diffusion equation inside the reactor core. Here the spatial discretization of this equation is done ...

Mostrando ítems 1-2 de 2