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 Year : 2020

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

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1

M.-H. Do

Function : Author

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

F. Madiot

Function : Author

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

Patrick Ciarlet

Function : Author
PersonId : 4372
IdHAL : patrick-ciarlet
ORCID : 0000-0003-1198-5063
IdRef : 11602531X

CV

Keywords

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

Domains

Nuclear Experiment [nucl-ex] Nuclear Theory [nucl-th]

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https://hal-cea.archives-ouvertes.fr/cea-02613567

Submitted on : Wednesday, May 20, 2020-11:19:52 AM

Last modification on : Sunday, June 26, 2022-12:30:44 AM

Dates and versions

cea-02613567 , version 1 (20-05-2020)

Identifiers

HAL Id : cea-02613567 , version 1

Cite

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⟩

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

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