DEL NEVO, ALESSANDRO
 Distribuzione geografica
Continente #
NA - Nord America 4.175
EU - Europa 4.152
AS - Asia 1.793
SA - Sud America 553
AF - Africa 33
Continente sconosciuto - Info sul continente non disponibili 17
OC - Oceania 10
Totale 10.733
Nazione #
US - Stati Uniti d'America 3.854
IT - Italia 1.076
DE - Germania 944
CN - Cina 730
GB - Regno Unito 516
SG - Singapore 513
BR - Brasile 495
SE - Svezia 436
FI - Finlandia 371
CA - Canada 299
RU - Federazione Russa 296
HK - Hong Kong 290
FR - Francia 167
BE - Belgio 69
NL - Olanda 67
AT - Austria 66
VN - Vietnam 59
IN - India 47
JP - Giappone 26
GR - Grecia 23
AR - Argentina 21
CH - Svizzera 21
RO - Romania 17
EU - Europa 15
UA - Ucraina 15
CO - Colombia 12
PK - Pakistan 12
TR - Turchia 12
ES - Italia 11
HU - Ungheria 11
MA - Marocco 11
UZ - Uzbekistan 11
IQ - Iraq 10
KR - Corea 10
KZ - Kazakistan 9
PL - Polonia 9
CZ - Repubblica Ceca 8
MX - Messico 8
ZA - Sudafrica 8
AU - Australia 7
AZ - Azerbaigian 7
BD - Bangladesh 7
EC - Ecuador 7
JO - Giordania 7
VE - Venezuela 7
IR - Iran 6
TH - Thailandia 6
TN - Tunisia 6
AL - Albania 5
IE - Irlanda 5
JM - Giamaica 5
OM - Oman 5
PT - Portogallo 5
CL - Cile 4
IL - Israele 4
PA - Panama 4
SK - Slovacchia (Repubblica Slovacca) 4
AE - Emirati Arabi Uniti 3
NP - Nepal 3
PY - Paraguay 3
AM - Armenia 2
BO - Bolivia 2
CR - Costa Rica 2
DO - Repubblica Dominicana 2
DZ - Algeria 2
EG - Egitto 2
GE - Georgia 2
IS - Islanda 2
KW - Kuwait 2
LB - Libano 2
LT - Lituania 2
LV - Lettonia 2
NZ - Nuova Zelanda 2
PE - Perù 2
SA - Arabia Saudita 2
TW - Taiwan 2
XK - ???statistics.table.value.countryCode.XK??? 2
AO - Angola 1
DK - Danimarca 1
GA - Gabon 1
KE - Kenya 1
LA - Repubblica Popolare Democratica del Laos 1
LU - Lussemburgo 1
MD - Moldavia 1
ML - Mali 1
NI - Nicaragua 1
PF - Polinesia Francese 1
PH - Filippine 1
PS - Palestinian Territory 1
QA - Qatar 1
SI - Slovenia 1
Totale 10.733
Città #
Chandler 1.180
Munich 374
Santa Clara 372
Boardman 294
San Mateo 285
Toronto 281
Ashburn 267
Southend 267
Hamburg 261
Helsinki 245
Hong Kong 241
Singapore 141
New York 139
Beijing 125
Rome 121
Berlin 109
Lappeenranta 102
Los Angeles 79
Milan 67
Miami 63
Brussels 60
Turin 59
Dong Ket 58
Las Vegas 57
Shanghai 56
Falkenstein 54
Guangzhou 50
Marseille 48
Vienna 47
Redwood City 39
Ann Arbor 38
Washington 32
Mountain View 30
Nuremberg 29
São Paulo 29
Council Bluffs 28
Bologna 27
Trenton 26
Pisa 22
Central 21
Amsterdam 19
Frankfurt am Main 17
Mazzano Romano 17
Tortona 17
Wilmington 17
Belo Horizonte 16
Tokyo 16
Jyväskylä 15
The Dalles 15
Chicago 14
Lyon 14
Falls Church 12
Paris 12
Richardson 12
Shenzhen 12
Qingdao 11
Cham 10
Düsseldorf 10
Rio de Janeiro 10
Serra 10
Tashkent 10
Budapest 9
Lucca 9
Redmond 9
Xian 9
Borås 8
Bucharest 8
Campinas 8
Fortaleza 8
London 8
Neive 8
Ribeirão Preto 8
San Nicola 8
St Petersburg 8
Venice 8
Bra 7
Darien 7
Ferrara 7
Florence 7
Santo André 7
Stockholm 7
Zhengzhou 7
Amman 6
Baku 6
Brasília 6
Chongqing 6
Curitiba 6
Genoa 6
Jinan 6
Nanjing 6
Padova 6
Palermo 6
Pavia 6
Almaty 5
Bergamo 5
Boydton 5
Central District 5
Chengdu 5
Goiânia 5
Guarulhos 5
Totale 6.375
Nome #
ALFRED-SGBT. Preliminary characterization by the HERO test section 221
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 220
Coupled simulations of natural and forced circulation tests in Nacie facility using relap5 and Ansys fluent codes 218
Assessment of SIMMER-III code in predicting water cooled lithium lead breeding blanket “in-box-Loss of Coolant Accident” 212
Caratterizzazione sperimentale dell'interazione metallo liquido pesante - acqua e qualifica rottura generatore di vapore LFR 209
Overview on lead-cooled fast reactor design and related technologies development in ENEA 190
Experimental campaign in support of the safety studies of the STGR in LFR 180
Pre-test analysis of thermal-hydraulic behaviour of the NACIE facility for the characterization of a fuel pin bundle 172
Characterization of leak detection in HLM system using LIFUS5/MOD3 facility 171
Status of Pb-16Li technologies for European DEMO fusion reactor 165
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione 149
GEN-IV LFR development: Status & perspectives 147
Optimization of the first wall cooling system for the DEMO WCLL blanket 138
Analisi del comportamento del combustibile MOX ad elevato burnup in condizioni di normal operation e DBA 134
Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives 134
Modeling and analysis of nuclear fuel pin behavior for innovative lead cooled FBR 133
Development of best estimate numerical tools for LFR design and safety analysis 124
CIRCE experimental set-up design and test matrix definition 121
Development and validation of an approach and numerical models for safety analysis of FBR 121
Analisi di pre-test della campagna sperimentale CIRCE/HERO con codici di sistema 116
Development of best estimate numerical tools for LFR design and safety analysis (2018) 112
Post-test of the sgtr experimental tests carried out in the LIFUS facility 110
Development of best estimate numerical tools for LFR design and safety analysis 108
Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data 107
Experimental investigation in LIFUS5/Mod2 facility of spiral-tube steam Generator Rupture scenarios for ELFR 106
Advancement in FGR modeling for transient analysis of FR fuel 106
Activities in Support to the Assessment of Steam Generator Bayonet Tubes, for GEN-IV Applications 105
Experimental and numerical investigations of interaction between heavy liquid metal and water for supporting the safety of LFR GEN. IV reator design 103
DEMO port plug design and integration studies 100
Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code 98
Progettazione e implementazione di un sistema per la rilevazione di piccole perdite. Design and follow-up of a LBE/water leakage detection system 97
RELAP5-3D three-dimensional analysis based on Phénix dissymmetric transient test 97
Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER 96
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications 95
MHD issues related to the use of Lithium Lead eutectic as breeder material for blankets of fusion power plants 94
Experimental investigation of spiral tubes steam generator rupture scenarios in LIFUS5/MOD2 facility for ELFR 94
Preliminary system modeling for the EUROfusion water cooled lithium lead blanket 93
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR 91
ALFRED-SGBT. Preliminary characterization by the HERO test section 91
Investigation on cooling performance of WCLL breeding blanket first wall for EU DEMO 91
Alternative design of DEMO Water Cooled Lithium Lead internal structure 89
Parametric study of the influence of double-walled tubes layout on the DEMO WCLL breeding blanket thermal performances 89
Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility 87
Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water 87
Test di caratterizzazione sperimentale del sistema per la rilevazione di piccole perdite nel Generatore di Vapore LFR 86
Development of a SIMMERRELAP5 coupling tool 86
Steam Generator mock-up preliminary design suitable for Pb-Li technology demonstration and code assessment 86
Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module 86
Qualification of TRACE V5.0 code against fast cooldown transient in the pkl-iii integral test facility 85
Divertor Tokamak Test facility project: status of design and implementation 84
Experimental Characterization of Leak Detection Systems in HLM Pool Using LIFUS5/Mod3 Facility 84
Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code 83
Development of the neutronic module and benchmark and validation of the thermal-hydraulic module of the FRENETIC code 83
On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances 83
RELAP5/SIMMER-III code coupling development for PbLi-water interaction 82
Assessment of SIMMER-III code based on steam generator tube rupture experiments in LIFUS5/Mod2 facility 82
Design dell’esperimento e specifica tecnica di fornitura relativa all’up-grade dell’impianto LIFUS5/Mod2 81
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project 81
Simulation study of pressure trends in the case of loss of coolant accident in Water Cooled Lithium Lead blanket module 80
Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges 79
Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop 78
Thermal-hydraulic analysis of the DEMO WCLL elementary cell: BZ tubes layout optimization 78
Sviluppo e validazione di un approccio e di modelli per le analisi di sicurezza di reattori veloci di IV generazione 77
Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor 77
Nuclear analysis of the Water cooled lithium lead DEMO reactor 76
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems 76
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 76
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System 75
MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization 75
Design of a Prototypical Mock-Up for the Experimental Investigation of WCLL First-Wall Performances 74
Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket 74
Hero test section for experimental investigation of steam generator bayonet tube of ALFRED 74
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation 74
EBR-II passive safety demonstration tests benchmark analyses-phase 2 73
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response 72
Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments 72
Updated design of water-cooled breeder blanket for CFETR 72
Influence of PbLi hydraulic path and integration layout on MHD pressure losses 71
Fornitura scambiatore di calore a tubi a baionetta 70
On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour 69
Deterministic safety analysis of Station Blackout postulated accident on the basis of the SMR simulator MASLWR 68
Post-test analysis of SHRT45R transient performed on the EBR-II FR 68
Supporto alla progettazione del combustibile nucleare per il reattore LFR 68
Validazione e analisi dei gas di fissione in combustibili MOX ad elevato burnup 68
Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design 68
Nuclear performances of the water-cooled lithium lead DEMO reactor: Neutronic analysis on a fully heterogeneous model 67
Systems engineering activities supporting the heating & current drive and fuelling lines systems integration in the European DEMO breeding blanket 67
System thermal-hydraulic modelling of the phénix dissymmetric test benchmark 67
MHD pressure drop estimate for the WCLL in-magnet PbLi loop 67
The demo water-cooled lead–lithium breeding blanket: Design status at the end of the pre-conceptual design phase 67
Preliminary analysis of an in-box LOCA in the breeding unit of the WCLL TBM for the ITER reactor with SIMMER-IV code 66
Validation of the 1D+2D thermal-hydraulic module of the FRENETIC code 66
Installazione della sezione di prova Hero nella facility Circe: sviluppo nodalizzazione e progettazione della campagna sperimentale 66
Preliminary design of a helical coil steam generator mock-up for the CIRCE facility for the development of DEMO LiPb heat exchanger 65
Experimental investigation and SIMMER-III code modelling of LBE-water interaction in LIFUS5/Mod2 facility 65
Hybrid 1D + 2D modelling for the assessment of the heat transfer in the EU DEMO water-cooled lithium-lead manifolds 65
Preliminary Thermo-Mechanical Design of the Once through Steam Generator and Molten Salt Intermediate Heat Exchanger for EU DEMO 65
Qualification of a RELAP5-3D © system code nodalization of EBR-II 64
IAEA's coordinated research project on EBR-II Shutdown heat removal tests 63
Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor 63
Totale 9.758
Categoria #
all - tutte 64.756
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 64.756


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/202063 0 0 0 0 0 0 0 0 0 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
2023/20241.822 109 69 201 44 145 350 97 155 114 148 128 262
2024/20254.033 75 396 114 169 543 446 661 601 692 336 0 0
Totale 10.972