Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project A Del Nevo, P Arena, G Caruso, P Chiovaro, PA Di Maio, M Eboli, ... Fusion Engineering and Design 146, 1805-1809, 2019 | 173 | 2019 |
GEN-IV LFR development: status & perspectives P Lorusso, S Bassini, A Del Nevo, I Di Piazza, F Giannetti, M Tarantino, ... Progress in Nuclear Energy 105, 318-331, 2018 | 170 | 2018 |
WCLL breeding blanket design and integration for DEMO 2015: status and perspectives A Del Nevo, E Martelli, P Agostini, P Arena, G Bongiovì, G Caruso, ... Fusion Engineering and Design 124, 682-686, 2017 | 146 | 2017 |
Corrosion and radiation resistant nanoceramic coatings for lead fast reactors FG Ferré, A Mairov, D Iadicicco, M Vanazzi, S Bassini, M Utili, M Tarantino, ... Corrosion Science 124, 80-92, 2017 | 127 | 2017 |
Heat transfer on HLM cooled wire-spaced fuel pin bundle simulator in the NACIE-UP facility I Di Piazza, M Angelucci, R Marinari, M Tarantino, N Forgione Nuclear Engineering and Design 300, 256-267, 2016 | 86 | 2016 |
Integral Circulation Experiment: Thermal–hydraulic simulator of a heavy liquid metal reactor M Tarantino, P Agostini, G Benamati, G Coccoluto, P Gaggini, V Labanti, ... Journal of nuclear materials 415 (3), 433-448, 2011 | 66 | 2011 |
A CFD analysis of flow blockage phenomena in ALFRED LFR demo fuel assembly I Di Piazza, F Magugliani, M Tarantino, A Alemberti Nuclear Engineering and Design 276, 202-215, 2014 | 64 | 2014 |
ALFRED reactor coolant system design A Alemberti, M Caramello, M Frignani, G Grasso, F Merli, G Morresi, ... Nuclear engineering and design 370, 110884, 2020 | 61 | 2020 |
Mixed convection and stratification phenomena in a heavy liquid metal pool M Tarantino, D Martelli, G Barone, I Di Piazza, N Forgione Nuclear Engineering and Design 286, 261-277, 2015 | 58 | 2015 |
Heavy liquid metal natural circulation in a one-dimensional loop G Coccoluto, P Gaggini, V Labanti, M Tarantino, W Ambrosini, N Forgione, ... Nuclear Engineering and Design 241 (5), 1301-1309, 2011 | 54 | 2011 |
HLM fuel pin bundle experiments in the CIRCE pool facility D Martelli, N Forgione, I Di Piazza, M Tarantino Nuclear Engineering and Design 292, 76-86, 2015 | 49 | 2015 |
Experimental study on gas-injection enhanced circulation performed with the CIRCE facility G Benamati, C Foletti, N Forgione, F Oriolo, G Scaddozzo, M Tarantino Nuclear Engineering and Design 237 (7), 768-777, 2007 | 49 | 2007 |
Overview on lead-cooled fast reactor design and related technologies development in ENEA M Tarantino, M Angiolini, S Bassini, S Cataldo, C Ciantelli, C Cristalli, ... Energies 14 (16), 5157, 2021 | 47 | 2021 |
Development of anti-permeation and corrosion barrier coatings for the WCLL breeding blanket of the European DEMO M Utili, S Bassini, S Cataldo, F Di Fonzo, M Kordac, T Hernandez, ... Fusion Engineering and Design 170, 112453, 2021 | 37 | 2021 |
ALFRED: A revised concept to improve pool related thermal-hydraulics M Frignani, A Alemberti, M Tarantino Nuclear Engineering and Design 355, 110359, 2019 | 33 | 2019 |
CFD thermo-hydraulic analysis of the CIRCE fuel bundle D Martelli, R Marinari, G Barone, I Di Piazza, M Tarantino Annals of nuclear energy 103, 294-305, 2017 | 33 | 2017 |
Materials for sustainable nuclear energy: a European strategic research and innovation agenda for all reactor generations L Malerba, A Al Mazouzi, M Bertolus, M Cologna, P Efsing, A Jianu, ... Energies 15 (5), 1845, 2022 | 32 | 2022 |
Status of Pb-16Li technologies for European DEMO fusion reactor M Utili, S Bassini, L Boccaccini, L Bühler, F Cismondi, A Del Nevo, ... Fusion Engineering and Design 146, 2676-2681, 2019 | 32 | 2019 |
Experimental analysis of stationary and transient scenarios of alfred steam generator bayonet tube in circe-hero facility P Lorusso, A Pesetti, M Tarantino, V Narcisi, F Giannetti, N Forgione, ... Nuclear Engineering and Design 352, 110169, 2019 | 29 | 2019 |
Pool CFD modelling: lessons from the SESAME project V Moreau, M Profir, A Alemberti, M Frignani, F Merli, M Belka, O Frybort, ... Nuclear Engineering and Design 355, 110343, 2019 | 28 | 2019 |