G. Veredas

Design and qualification of an on-line permeator for the recovery of tritium from lead–lithium eutectic breeding alloy

G. Veredas, J. Fradera, Iván Fernández et al. · Fusion Engineering and Design · 2011 · 14 citations

Materials Science, Chemical Engineering, Engineering +4

Neutronic design studies of a conceptual DCLL fusion reactor for a DEMO and a commercial power plant

Iole Palermo, G. Veredas, J.M. Gómez-Ros et al. · Nuclear Fusion · 2015 · 11 citations

Engineering, Nuclear Engineering, Dcll Reactor +14

Neutronic analysis of a dual He/LiPb coolant breeding blanket for DEMO

J.P. Catalán, F. Ogando, J. Sanz et al. · Fusion Engineering and Design · 2011 · 10 citations

Neutronic Analysis, Nuclear Physics, Physics +6

Neutronic design analyses for a dual-coolant blanket concept: Optimization for a fusion reactor DEMO

Iole Palermo, J.M. Gómez-Ros, G. Veredas et al. · Fusion Engineering and Design · 2012 · 10 citations

Dual-coolant Blanket Concept, Engineering, Neutronic Design +6