Jean-Christophe Dumas

Thermodynamic modelling of advanced oxide and carbide nuclear fuels: Description of the U–Pu–O–C systems

Christine Guéneau, N. Dupin, Bo Sundman et al. · Journal of Nuclear Materials · 2011 · 218 citations · Full text

Engineering, Nuclear Engineering, Physics +16

GERMINAL, a fuel performance code of the PLEIADES platform to simulate the in-pile behaviour of mixed oxide fuel pins for sodium-cooled fast reactors

M. Lainet, Bruno Michel, Jean-Christophe Dumas et al. · Journal of Nuclear Materials · 2018 · 65 citations

Engineering, Nuclear Engineering, Nuclear Fuel Cycle +16

An improved method to evaluate the “Joint Oxyde-Gaine” formation in (U,Pu)O₂ irradiated fuels using the GERMINAL V2 code coupled to Calphad thermodynamic computations

Karl Samuelsson, Jean-Christophe Dumas, Bo Sundman et al. · EPJ Nuclear Sciences & Technologies · 2020 · 10 citations · Full text

Natural Sciences, Chemistry, Nuclear Engineering +16