The virtual environment for reactor applications (VERA): design and architecture, Journal of Computational Physics, vol.326, pp.544-568, 2016. ,
Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers, Annals of Nuclear Energy, vol.62, pp.357-374, 2013. ,
Neutronics/Fuel Thermomecanics coupling in the Framework of a REA (Rod Ejection Accident) Transient Scenario Calculation, Proc. Int. Conf. Physics of Reactors (PHYSOR2016) ,
,
APOLLO3®: CEA/DEN deterministic multi-purpose code for reactor physics analysis, Proc. Int. Conf. Physics of Reactors (PHYSOR2016) ,
URL : https://hal.archives-ouvertes.fr/cea-02509714
THEDI: a multi-1D two-phase flow solver for neutronic codes, Proc. ICAPP2019 ,
FLICA4: a three dimensional two-phase flow computer code with advanced numerical methods for nuclear applications, Nuclear Engineering and Design, pp.139-155, 2000. ,
Accelerated polynomial axial expansions for full 3D neutron transport MOC in the APOLLO3® code system as applied to the ASTRID fast breeder reactor, Annals of Nuclear Energy, vol.113, pp.194-236, 2018. ,
The SPH homogenization method, Proc. Specialists' Mtg. Homogenization Methods in Reactor Physics, 1978. ,
An analysis of reflector homogenization techniques for full core diffusion calculations, Nuclear Science and Engineering, vol.168, issue.1, pp.59-72, 2011. ,
A neutron transport characteristics method for 3D axially extruded geometries coupled with a fine group self-shielding environment, Nuclear Science and Engineering, vol.186, issue.3, pp.239-276, 2017. ,
URL : https://hal.archives-ouvertes.fr/cea-02381240
MINOS : A simplified Pn solver for core calculation, Nuclear Science and Engineering, vol.155, issue.2, pp.250-263, 2007. ,
Minaret, a deterministic neutron transport solver for nuclear core calculations, 2011. ,
URL : https://hal.archives-ouvertes.fr/cea-00545919
, The HDF group