Development and validation of a thermal-hydraulic transient model capable to analyze the TBM for ITER and the Breeding Blanket for the EU-DEMO reactor
cun id:
872
FUSIONE NUCLEARE
The differentially-tilted toroidal field coil concept for tokamaks.
Liquid metal MHD flows in water-cooled test blanket module for ITER
Optimization of Water-Cooled Lithium Lead blanket cooling system via thermal-hydraulic transient analysis
Development and validation of a thermal-hydraulic model of helical coil liquid metal steam generators for design and safety analyses of innovative fission and fusion nuclear plants
3D MHD analysis of prototypical manifold for liquid metal blankets
Shock wave propagation in liquid metal with an applied static magnetic field
Extreme magnetoconvection in shallow horizontally heated cavities: direct numerical simulation and preliminary test section design
Thermal-hydraulic analysis of the EU-DEMO WCLL Breeding Blanket systems during a Loss Of Flow Accident
Studi esplorativi sulle potenzialità di un sistema nucleare ibrido fusione-fissione compatto ad alto campo magnetico a contribuire alla sostenibiltà dell'energia nucleare.