DEL NEVO, ALESSANDRO
 Distribuzione geografica
Continente #
NA - Nord America 3.369
EU - Europa 2.509
AS - Asia 660
Continente sconosciuto - Info sul continente non disponibili 15
OC - Oceania 8
SA - Sud America 3
AF - Africa 2
Totale 6.566
Nazione #
US - Stati Uniti d'America 3.077
IT - Italia 831
GB - Regno Unito 503
SE - Svezia 434
CN - Cina 403
CA - Canada 291
DE - Germania 204
FI - Finlandia 173
FR - Francia 117
HK - Hong Kong 99
BE - Belgio 65
VN - Vietnam 58
AT - Austria 55
IN - India 43
GR - Grecia 22
RU - Federazione Russa 21
NL - Olanda 18
JP - Giappone 17
EU - Europa 15
RO - Romania 15
SG - Singapore 15
CH - Svizzera 12
HU - Ungheria 9
ES - Italia 8
UA - Ucraina 8
KR - Corea 7
AU - Australia 6
TH - Thailandia 6
IR - Iran 5
PL - Polonia 4
CZ - Repubblica Ceca 3
IE - Irlanda 3
TR - Turchia 3
PK - Pakistan 2
AR - Argentina 1
BR - Brasile 1
CO - Colombia 1
DZ - Algeria 1
LU - Lussemburgo 1
MD - Moldavia 1
MX - Messico 1
NZ - Nuova Zelanda 1
PF - Polinesia Francese 1
PT - Portogallo 1
SA - Arabia Saudita 1
SI - Slovenia 1
TW - Taiwan 1
ZA - Sudafrica 1
Totale 6.566
Città #
Chandler 1.180
San Mateo 285
Toronto 275
Southend 267
Ashburn 250
Boardman 166
Beijing 116
Berlin 109
New York 108
Lappeenranta 102
Rome 96
Helsinki 71
Dong Ket 58
Las Vegas 57
Brussels 56
Hong Kong 52
Los Angeles 50
Marseille 46
Milan 46
Shanghai 42
Vienna 41
Guangzhou 39
Redwood City 39
Ann Arbor 38
Turin 35
Washington 32
Mountain View 30
Bologna 27
Trenton 26
Central 21
Miami 20
Mazzano Romano 17
Tortona 17
Wilmington 17
Chicago 14
Pisa 13
Falls Church 12
Richardson 12
Paris 11
Qingdao 10
Tokyo 10
Budapest 9
Redmond 9
Serra 9
Xian 9
Borås 8
Neive 8
San Nicola 8
Venice 8
Bra 7
Bucharest 7
Darien 7
London 7
Shenzhen 7
Cham 6
Ferrara 6
Frankfurt am Main 6
Genoa 6
Lyon 6
Padova 6
Palermo 6
St Petersburg 6
Zhengzhou 6
Bergamo 5
Central District 5
Chongqing 5
Florence 5
Karlsruhe 5
Leopoldshafen 5
Nanjing 5
Rockville 5
Stockholm 5
Stuttgart 5
Tappahannock 5
Varese 5
Woodbridge 5
Castel Frentano 4
Chengdu 4
Como 4
Fredericton 4
Guiyang 4
Hanover 4
Mississauga 4
Mol 4
Nembro 4
Noicattaro 4
Pavia 4
Pescia 4
Raleigh 4
West Jordan 4
Xi'an 4
Ancona 3
Aprilia 3
Bang Klam 3
Bangalore 3
Bangkok 3
Bastia umbra 3
Fasano 3
Fossano 3
Garching 3
Totale 4.222
Nome #
Characterization of leak detection in HLM system using LIFUS5/MOD3 facility 144
Experimental campaign in support of the safety studies of the STGR in LFR 138
Pre-test analysis of thermal-hydraulic behaviour of the NACIE facility for the characterization of a fuel pin bundle 131
Overview on lead-cooled fast reactor design and related technologies development in ENEA 124
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione 120
GEN-IV LFR development: Status & perspectives 104
CIRCE experimental set-up design and test matrix definition 100
Analisi del comportamento del combustibile MOX ad elevato burnup in condizioni di normal operation e DBA 99
Modeling and analysis of nuclear fuel pin behavior for innovative lead cooled FBR 99
Development and validation of an approach and numerical models for safety analysis of FBR 97
Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives 96
Development of best estimate numerical tools for LFR design and safety analysis 93
Advancement in FGR modeling for transient analysis of FR fuel 83
Development of best estimate numerical tools for LFR design and safety analysis (2018) 82
RELAP5-3D three-dimensional analysis based on Phénix dissymmetric transient test 82
Development of best estimate numerical tools for LFR design and safety analysis 80
Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER 77
Progettazione e implementazione di un sistema per la rilevazione di piccole perdite. Design and follow-up of a LBE/water leakage detection system 75
Experimental and numerical investigations of interaction between heavy liquid metal and water for supporting the safety of LFR GEN. IV reator design 74
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR 74
Analisi di pre-test della campagna sperimentale CIRCE/HERO con codici di sistema 74
Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code 74
Experimental investigation in LIFUS5/Mod2 facility of spiral-tube steam Generator Rupture scenarios for ELFR 71
Qualification of TRACE V5.0 code against fast cooldown transient in the pkl-iii integral test facility 70
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR 68
DEMO port plug design and integration studies 66
Activities in Support to the Assessment of Steam Generator Bayonet Tubes, for GEN-IV Applications 66
MHD issues related to the use of Lithium Lead eutectic as breeder material for blankets of fusion power plants 65
Preliminary system modeling for the EUROfusion water cooled lithium lead blanket 65
Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility 65
Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module 65
Parametric study of the influence of double-walled tubes layout on the DEMO WCLL breeding blanket thermal performances 64
Thermal-hydraulic analysis of the DEMO WCLL elementary cell: BZ tubes layout optimization 64
Experimental Characterization of Leak Detection Systems in HLM Pool Using LIFUS5/Mod3 Facility 63
Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water 62
Optimization of the first wall cooling system for the DEMO WCLL blanket 60
Design dell’esperimento e specifica tecnica di fornitura relativa all’up-grade dell’impianto LIFUS5/Mod2 59
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project 59
Assessment of SIMMER-III code based on steam generator tube rupture experiments in LIFUS5/Mod2 facility 59
Steam Generator mock-up preliminary design suitable for Pb-Li technology demonstration and code assessment 59
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 58
Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code 58
Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop 58
ALFRED-SGBT. Preliminary characterization by the HERO test section 58
ALFRED-SGBT. Preliminary characterization by the HERO test section 58
Sviluppo e validazione di un approccio e di modelli per le analisi di sicurezza di reattori veloci di IV generazione 58
Alternative design of DEMO Water Cooled Lithium Lead internal structure 58
On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances 57
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems 57
Integrated design of breeding blanket and ancillary systems related to the use of helium or water as a coolant and impact on the overall plant design 57
Post-test of the sgtr experimental tests carried out in the LIFUS facility 56
Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data 56
Development of a SIMMERRELAP5 coupling tool 55
Coupled simulations of natural and forced circulation tests in Nacie facility using relap5 and Ansys fluent codes 55
Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments 55
Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket 54
Fornitura scambiatore di calore a tubi a baionetta 54
Investigation on cooling performance of WCLL breeding blanket first wall for EU DEMO 54
Status of Pb-16Li technologies for European DEMO fusion reactor 54
MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization 53
Hero test section for experimental investigation of steam generator bayonet tube of ALFRED 53
The demo water-cooled lead–lithium breeding blanket: Design status at the end of the pre-conceptual design phase 53
Deterministic safety analysis of Station Blackout postulated accident on the basis of the SMR simulator MASLWR 52
Experimental investigation of spiral tubes steam generator rupture scenarios in LIFUS5/MOD2 facility for ELFR 52
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications 52
Nuclear analysis of the Water cooled lithium lead DEMO reactor 52
System thermal-hydraulic modelling of the phénix dissymmetric test benchmark 51
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response 51
RELAP5/SIMMER-III code coupling development for PbLi-water interaction 51
Influence of PbLi hydraulic path and integration layout on MHD pressure losses 51
Validation of the 1D+2D thermal-hydraulic module of the FRENETIC code 50
Updated design of water-cooled breeder blanket for CFETR 50
Qualification of a RELAP5-3D © system code nodalization of EBR-II 49
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation 49
Caratterizzazione sperimentale dell'interazione metallo liquido pesante - acqua e qualifica rottura generatore di vapore LFR 48
Installazione della sezione di prova Hero nella facility Circe: sviluppo nodalizzazione e progettazione della campagna sperimentale 48
Post-test analysis of SHRT45R transient performed on the EBR-II FR 48
On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour 48
Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges 47
Systems engineering activities supporting the heating & current drive and fuelling lines systems integration in the European DEMO breeding blanket 47
IAEA's coordinated research project on EBR-II Shutdown heat removal tests 46
Supporto alla progettazione del combustibile nucleare per il reattore LFR 46
Experimental analysis of stationary and transient scenarios of alfred steam generator bayonet tube in circe-hero facility 46
EBR-II passive safety demonstration tests benchmark analyses-phase 2 46
Experimental investigation and SIMMER-III code modelling of LBE-water interaction in LIFUS5/Mod2 facility 45
Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design 45
Hybrid 1D + 2D modelling for the assessment of the heat transfer in the EU DEMO water-cooled lithium-lead manifolds 45
Preliminary Thermo-Mechanical Design of the Once through Steam Generator and Molten Salt Intermediate Heat Exchanger for EU DEMO 45
Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor 44
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System 43
Qualifica di codici di calcolo dedicati alle analisi di sistema avanzati quando applicati nella simulazione di impianti a metallo liquido 43
Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor 43
MHD forced convection flow in dielectric and electro-conductive rectangular annuli 41
MHD pressure drop estimate for the WCLL in-magnet PbLi loop 41
Thermo-hydraulic analysis of PbLi ancillary system of WCLL TBM undergoing in-box LOCA 41
Experimental and numerical results of LIFUS5/Mod3 series E test on in-box LOCA transient for WCLL-BB 40
Thermal-hydraulic code-to-code benchmark in a simplified EBR-II geometry 39
Post-test simulation of a PLOFA transient test in the CIRCE-HERO facility 39
Validazione e analisi dei gas di fissione in combustibili MOX ad elevato burnup 38
Nuclear performances of the water-cooled lithium lead DEMO reactor: Neutronic analysis on a fully heterogeneous model 37
Totale 6.248
Categoria #
all - tutte 45.733
article - articoli 0
book - libri 0
conference - conferenze 0
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 45.733


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/2020161 0 0 0 0 8 17 47 15 11 23 17 23
2020/20211.057 13 19 10 19 172 10 24 99 86 123 346 136
2021/20221.323 39 320 55 75 154 33 63 271 82 25 71 135
2022/20232.576 191 478 182 372 98 433 44 227 330 83 69 69
2023/20241.671 109 69 201 44 145 350 97 155 114 148 128 111
Totale 6.788