Adaptive solution of the neutron diffusion equation with heterogeneous coefficients using the mixed finite element method on structured meshes

M.-H. Do; F. Madiot; Patrick Ciarlet

Conference papers

Adaptive solution of the neutron diffusion equation with heterogeneous coefficients using the mixed finite element method on structured meshes

M.-H. Do ¹ F. Madiot ¹ Patrick Ciarlet

1 CEA-DES (ex-DEN) - CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire)

Keywords : adaptive mesh refinement. a posteriori error estimates eigenvalue problem diffusion equation Neutronics

Document type :

Conference papers

Domain :

Physics [physics] / Nuclear Experiment [nucl-ex]

Physics [physics] / Nuclear Theory [nucl-th]

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https://hal-cea.archives-ouvertes.fr/cea-02613567
Contributor : Bibliothèque Cadarache <>
Submitted on : Wednesday, May 20, 2020 - 11:19:52 AM
Last modification on : Monday, August 24, 2020 - 3:10:51 PM

Adaptive solution of the neutron diffusion equation with heterogeneous coefficients using the mixed finite element method on structured meshes

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Adaptive solution of the neutron diffusion equation with heterogeneous coefficients using the mixed finite element method on structured meshes

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