%0 Conference Paper %F Oral %T Adaptive solution of the neutron diffusion equation with heterogeneous coefficients using the mixed finite element method on structured meshes %+ CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)) %A Do, M.-H. %A Madiot, F. %A Ciarlet, Patrick %< avec comité de lecture %B PHYSOR 2020 TRANSITION TO A SCALABLE NUCLEAR FUTURE %C Cambridge, United Kingdom %8 2020-03-29 %D 2020 %K Neutronics %K diffusion equation %K eigenvalue problem %K a posteriori error estimates %K adaptive mesh refinement. %Z Physics [physics]/Nuclear Experiment [nucl-ex] %Z Physics [physics]/Nuclear Theory [nucl-th]Conference papers %G English %L cea-02613567 %U https://cea.hal.science/cea-02613567 %~ CEA %~ ENSTA %~ DSV %~ DEN %~ CEA-DRF