Neutron kinetic and Thermal-hydraulic coupled analisys of FFTF reactor Unprotected Loss of Flow transient
cun id:
844
FISSIONE NUCLEARE
Uncertainty quantification in RELAP5-3D© simulation of NACIE experimental facility focused on code validation
Studi esplorativi sulle potenzialità di un sistema nucleare ibrido fusione-fissione compatto ad alto campo magnetico a contribuire alla sostenibiltà dell'energia nucleare.
Experimental evaluation of pool boiling heat transfer coefficient at high thermal flux for a passive decay heat removal system to be used in fission and fusion power plant
Development of an innovative tool to perform a dynamic probabilistic risk assessment of nuclear power plants.
Preliminary Engineering Design of APRIL facility: a new facility for the characterization of anti-permeation coatings for fission and fusion applications