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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 : Neutronics diffusion equation eigenvalue problem a posteriori error estimates adaptive mesh refinement.
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Conference papers
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https://hal-cea.archives-ouvertes.fr/cea-02613567
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Submitted on : Wednesday, May 20, 2020 - 11:19:52 AM
Last modification on : Sunday, June 26, 2022 - 12:30:44 AM

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  • HAL Id : cea-02613567, version 1

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M.-H. Do, F. Madiot, Patrick Ciarlet. Adaptive solution of the neutron diffusion equation with heterogeneous coefficients using the mixed finite element method on structured meshes. PHYSOR 2020 TRANSITION TO A SCALABLE NUCLEAR FUTURE, Mar 2020, Cambridge, United Kingdom. ⟨cea-02613567⟩

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