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:
1057
IMPIANTI NUCLEARI
Neutron kinetic and Thermal-hydraulic coupled analisys of FFTF reactor Unprotected Loss of Flow transient
Thermal-hydraulic analysis of the EU-DEMO WCLL Breeding Blanket systems during a Loss Of Flow Accident
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.
Detailed thermal-hydraulic study of the EU-DEMO Water Cooled Lithium-Lead Breeding Blanket elementary cell