Fabien Perdu

Potential of thorium molten salt reactorsdetailed calculations and concept evolution with a view to large scale energy production

A. Nuttin, D. Heuer, A. Billebaud et al. · Progress in Nuclear Energy · 2005 · 305 citations · Full text

Engineering, Nuclear Engineering, Nuclear Fuel Cycle +15

Neutronic Studies in Support of Accelerator-Driven Systems: The MUSE Experiments in the MASURCA Facility

R. Soule, W. Assal, P. Chaussonnet et al. · Nuclear Science and Engineering · 2004 · 141 citations · Full text

Natural Sciences, Nuclear Engineering, Physics +15

Status of CATHARE code for sodium cooled fast reactors

D. Tenchine, Roland Bavière, Philippe Bazin et al. · Nuclear Engineering and Design · 2012 · 56 citations

Engineering, Electrical Engineering, Nuclear Engineering +14

A first system/CFD coupled simulation of a complete nuclear reactor transient using CATHARE2 and TRIO_U. Preliminary validation on the Phénix Reactor Natural Circulation Test

Roland Bavière, Nicolas Tauveron, Fabien Perdu et al. · Nuclear Engineering and Design · 2014 · 53 citations

Engineering, Nuclear Engineering, Physics +17

Overview of the system alone and system/CFD coupled calculations of the PHENIX Natural Circulation Test within the THINS project

D. Pialla, D. Tenchine, S. Li et al. · Nuclear Engineering and Design · 2015 · 42 citations

Natural Sciences, Earth Sciences, Physics +9