Sfoglia per Rivista NUCLEAR ENGINEERING AND DESIGN
Advanced Thermal-Hydraulic experiments and instrumentation for heavy liquid metal reactors
2022-01-01 Pacio, J.; Van Tichelen, K.; Eckert, S.; Wondrak, T.; Di Piazza, I.; Lorusso, P.; Tarantino, M.; Daubner, M.; Litfin, K.; Ariyoshi, G.; Obayashi, H.; Sasa, T.
ALFRED reactor coolant system design
2020-01-01 Alemberti, A.; Caramello, M.; Frignani, M.; Grasso, G.; Merli, F.; Morresi, G.; Tarantino, M.
ALFRED: A revised concept to improve pool related thermal-hydraulics
2019-01-01 Frignani, M.; Alemberti, A.; Tarantino, M.
An alternative solution for heavy liquid metal cooled reactors fuel assemblies
2014-01-01 Peluso, V.
Analysis of solutions for passively activated safety shutdown devices for SFR
2013-01-01 Burgazzi, L.
ANTEO+: A subchannel code for thermal-hydraulic analysis of liquid metal cooled systems
2016-01-01 Mattioli, D.; Grasso, G.
Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors
2015-01-01 Polidori, M.; Bandini, G.
Assessment of the enhanced DHRS configuration for MYRRHA reactor
2016-01-01 Bandini, G.
ASTEC validation on TMI-2 and LOFT LP-FP-2
2014-01-01 De Rosa, F.; Bandini, G.
A Bayesian framework of inverse uncertainty quantification with principal component analysis and Kriging for the reliability analysis of passive safety systems
2021-01-01 Roma, G.; Di Maio, F.; Bersano, A.; Pedroni, N.; Bertani, C.; Mascari, F.; Zio, E.
Blockage fuel pin simulator experiments and simulation
2019-01-01 Marinari, R.; Di Piazza, I.; Tarantino, M.; Forgione, N.
A CFD analysis of flow blockage phenomena in ALFRED LFR demo fuel assembly
2014-01-01 Tarantino, M.; Di Piazza, I.
CIRCE-ICE PLOHS experimental campaign
2019-01-01 Martelli, D.; Tarantino, M.; Forgione, N.
Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking
2014-01-01 Bandini, G.
Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis
2014-01-01 Bandini, G.
The core design of ALFRED, a demonstrator for the European lead-cooled reactors
2014-01-01 Artioli, C.; Petrovich, C.; Grasso, G.; Mattioli, D.
European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems
2015-01-01 Bandini, G.
Experimental analysis of stationary and transient scenarios of alfred steam generator bayonet tube in circe-hero facility
2019-01-01 Lorusso, P.; Pesetti, A.; Tarantino, M.; Narcisi, V.; Giannetti, F.; Forgione, N.; Del Nevo, A.
Experimental campaign on the HLM loop NACIE-UP with instrumented wire-spaced fuel pin simulator
2018-01-01 Di Piazza, I.
Experimental investigation and SIMMER-III code modelling of LBE-water interaction in LIFUS5/Mod2 facility
2015-01-01 Del Nevo, A.
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