J. A. Turner, The virtual environment for reactor applications (VERA): design and architecture, Journal of Computational Physics, vol.326, pp.544-568, 2016.

Y. Jung and . Sang, Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers, Annals of Nuclear Energy, vol.62, pp.357-374, 2013.

L. Pallec and J. C. , Neutronics/Fuel Thermomecanics coupling in the Framework of a REA (Rod Ejection Accident) Transient Scenario Calculation, Proc. Int. Conf. Physics of Reactors (PHYSOR2016)

&. Salome,

D. Schneider, 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

C. Patricot, THEDI: a multi-1D two-phase flow solver for neutronic codes, Proc. ICAPP2019

I. Toumi, FLICA4: a three dimensional two-phase flow computer code with advanced numerical methods for nuclear applications, Nuclear Engineering and Design, pp.139-155, 2000.

S. Santandrea, L. Graziano, and D. Sciannandrone, 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.

A. Kavenoky, The SPH homogenization method, Proc. Specialists' Mtg. Homogenization Methods in Reactor Physics, 1978.

C. Sandrin, R. Sanchez, and F. Dolci, An analysis of reflector homogenization techniques for full core diffusion calculations, Nuclear Science and Engineering, vol.168, issue.1, pp.59-72, 2011.

S. Santandrea, 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

A. Baudron and J. Lautard, MINOS : A simplified Pn solver for core calculation, Nuclear Science and Engineering, vol.155, issue.2, pp.250-263, 2007.

J. Y. Moller and J. J. Lautard, Minaret, a deterministic neutron transport solver for nuclear core calculations, 2011.
URL : https://hal.archives-ouvertes.fr/cea-00545919

, The HDF group