ZAPPATORE, ANDREA
 Distribuzione geografica
Continente #
EU - Europa 2.730
NA - Nord America 2.709
AS - Asia 1.282
SA - Sud America 183
AF - Africa 136
Continente sconosciuto - Info sul continente non disponibili 1
OC - Oceania 1
Totale 7.042
Nazione #
US - Stati Uniti d'America 2.655
IT - Italia 1.374
CN - Cina 549
SG - Singapore 385
DE - Germania 286
GB - Regno Unito 221
BR - Brasile 169
FR - Francia 133
RU - Federazione Russa 132
CI - Costa d'Avorio 110
KR - Corea 108
BE - Belgio 85
FI - Finlandia 73
IE - Irlanda 69
CH - Svizzera 59
TR - Turchia 54
UA - Ucraina 49
BG - Bulgaria 48
NL - Olanda 47
AT - Austria 46
HK - Hong Kong 42
CA - Canada 40
SE - Svezia 27
ID - Indonesia 25
ES - Italia 22
JP - Giappone 19
IN - India 18
TG - Togo 14
JO - Giordania 12
VN - Vietnam 12
GR - Grecia 11
BD - Bangladesh 8
IQ - Iraq 8
MY - Malesia 8
TW - Taiwan 8
MX - Messico 7
RO - Romania 7
NO - Norvegia 6
PT - Portogallo 6
CO - Colombia 5
DK - Danimarca 5
HR - Croazia 5
PL - Polonia 5
UZ - Uzbekistan 5
LT - Lituania 4
SA - Arabia Saudita 4
AE - Emirati Arabi Uniti 3
AR - Argentina 3
AZ - Azerbaigian 3
IL - Israele 3
IR - Iran 3
KE - Kenya 3
SI - Slovenia 3
SN - Senegal 3
VE - Venezuela 3
OM - Oman 2
PK - Pakistan 2
TT - Trinidad e Tobago 2
A2 - ???statistics.table.value.countryCode.A2??? 1
AM - Armenia 1
AU - Australia 1
BB - Barbados 1
CL - Cile 1
CR - Costa Rica 1
CZ - Repubblica Ceca 1
DO - Repubblica Dominicana 1
DZ - Algeria 1
EC - Ecuador 1
EG - Egitto 1
EU - Europa 1
GE - Georgia 1
GN - Guinea 1
JM - Giamaica 1
KG - Kirghizistan 1
LA - Repubblica Popolare Democratica del Laos 1
LU - Lussemburgo 1
MA - Marocco 1
NG - Nigeria 1
NP - Nepal 1
PE - Perù 1
SV - El Salvador 1
TN - Tunisia 1
Totale 7.042
Città #
Ashburn 392
Turin 307
Chandler 246
Singapore 209
Torino 186
Southend 162
Council Bluffs 129
Fairfield 123
Abidjan 110
Princeton 103
Santa Clara 95
Seattle 94
Beijing 90
Houston 84
Milan 79
Brussels 77
Hefei 77
Rome 72
Ann Arbor 70
Cambridge 66
Berlin 63
Boardman 62
Dublin 62
Woodbridge 61
Sofia 48
Lappeenranta 45
Wilmington 45
Seoul 44
Munich 43
San Donato Milanese 34
San Ramon 34
Bern 30
San Mauro Torinese 28
Izmir 26
Jakarta 25
Vienna 21
Dallas 20
Jacksonville 20
New York 19
Istanbul 18
Nanjing 18
Nuremberg 18
Guangzhou 17
Los Angeles 17
San Francisco 17
Chengdu 16
Hong Kong 16
Shenzhen 16
Chicago 15
Turku 15
Lomé 14
Valfenera 14
Bari 13
Genoa 13
Naaldwijk 13
Salerno 13
Helsinki 12
Padova 12
Toronto 12
Frascati 11
Montréal 11
Naples 11
Piscataway 11
San Diego 11
Amsterdam 10
Bologna 10
Shanghai 10
Barcelona 9
Columbus 9
London 9
Redwood City 9
The Dalles 9
Borgaro Torinese 8
Jiaxing 8
Moscow 8
Paris 8
Varese 8
Washington 8
Wuhan 8
Borgosesia 7
Bremen 7
Cangzhou 7
Falls Church 7
Norwalk 7
São Paulo 7
Belo Horizonte 6
Boston 6
Cupertino 6
Gelsenkirchen 6
Karlsruhe 6
Leuven 6
Madrid 6
Oslo 6
Ribeirão Preto 6
San Antonio 6
Tokyo 6
Bengaluru 5
Cagliari 5
Changsha 5
Dearborn 5
Totale 4.114
Nome #
DTT - Divertor Tokamak Test facility - Interim Design Report 421
CFD Analysis of Mini-Channel Cooling for a Gyrotron Cavity 393
CFD Analysis of Different Cooling Options for a Gyrotron Cavity 383
Quench propagation in a TF coil of the EU DEMO 374
DTT device: Conceptual design of the superconducting magnet system 338
Performance analysis of the NbTi PF coils for the EU DEMO fusion reactor 230
Modelling of the test of the JT-60SA HTS current leads 210
Predictive 1-D thermal-hydraulic analysis of the prototype HTS current leads for the ITER correction coils 200
The DEMO magnet system – Status and future challenges 200
DTT: A Challenging Framework for a Sound Superconducting Magnets Design 195
3D transient CFD simulation of an in-vessel Loss-Of-Coolant Accident in the EU DEMO fusion reactor 179
Design, Test and Analysis of a Gyrotron Cavity Mock-Up Cooled Using Mini Channels 175
Modeling Quench Propagation in the ENEA HTS Cable-In-Conduit Conductor 174
CFD analysis of natural convection cooling of the in-vessel components during a shutdown of the EU DEMO fusion reactor 155
Modelling Innovative High Temperature Superconductors for Fusion Applications 154
Thermal-hydraulic test and analysis of the ENEA TF conductor sample for the EU DEMO fusion reactor 144
Analysis of the thermal-hydraulic effects of a plasma disruption on the DTT TF magnets 143
Thermal-hydraulic and mechanical analysis of the Beam Line Components for the DTT Neutral Beam Injector 142
AC Losses in the First ITER CS Module Tests: Experimental Results and Comparison to Analytical Models 130
Self Consistent Electrical and Thermal-Hydraulic Model of Faults in Superconducting Magnets: EU DEMO TF Short Circuit During a Fast Discharge 128
Validation of the 4C Code on the AC Loss Tests of a Full-Scale ITER Coil 126
AC Losses in the Second Module of the ITER Central Solenoid 125
Thermal-hydraulic analysis of the DTT Toroidal Field magnets in DC operation 121
3D Transient CFD Simulation of an In-Vessel Loss-of-Coolant Accident in the EU DEMO WCLL Breeding Blanket 116
3D-FOX—A 3D Transient Electromagnetic Code for Eddy Currents Computation in Superconducting Magnet Structures: DTT TF Fast Current Discharge Analysis 115
Development of the H4C Model of Quench Propagation in the ENEA HTS Cable-In-Conduit Conductor 114
Innovative concepts in the DTT neutral beam injector 112
A Transient 3-D CFD Model for the Simulation of Forced or Natural Convection of the EU DEMO In-Vessel Components 108
Advance in the conceptual design of the European DEMO magnet system 108
A new model for the analysis of quench in HTS cable-in-conduit conductors based on the twisted-stacked-tape cable concept for fusion applications 108
Effect of local defects on HTS fusion magnets performance 108
Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption 106
Thermal-hydraulic assessment of the Steam Generator mock-up for the EU DEMO WCLL using CFD co-simulation 103
Computational Thermal-Fluid Dynamics analyses of borated water distribution in the Vacuum Vessel of the Divertor Tokamak Test facility 97
Testing of the ITER Central Solenoid Modules 96
Development of an integrated thermo-mechanical simulation environment for quench analyses in HTS cables for fusion 95
Quench experiments on sub-size HTS Cable-In-Conduit Conductors for fusion applications: Data analysis and model validation 94
Overview of the 2018 Workshop On Iterative Errors in Unsteady Flow Simulations 94
Development and validation of the 4C thermal–hydraulic model of the ITER Central Solenoid modules 93
A critical assessment of thermal-hydraulic modeling of HTS Twisted-Stacked-Tape-Cable conductors for fusion applications 85
Assessment of the performance of a 20 kA REBCO current lead 78
First ITER CS module test results 73
Thermal-hydraulic analysis of the DTT CS and PF pulsed coil performance during AC operation 69
Coupling and Hysteresis Loss Measurements on the ITER CS Module #4 67
Impact of Hysteresis Losses in Hybrid (HTS-LTS) Coils for Fusion Applications 65
Thermal Hydraulic Behavior of the First ITER CS Module 65
Testing of the ITER CS Module #4 63
CFD analysis of natural convection cooling of the in-vessel components during a shutdown of the EU DEMO fusion reactor (dataset) 61
Feasibility analysis of partially insulated Nb3Sn EU DEMO toroidal field coil 48
DTT toroidal field conductor samples test in Sultan: DC and AC characterization 48
Full 3D thermal-hydraulic and electric modelling of quench propagation in HTS conductors 36
Totale 7.265
Categoria #
all - tutte 22.192
article - articoli 19.115
book - libri 839
conference - conferenze 1.466
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 43.612


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021351 0 0 15 46 25 21 28 45 30 59 27 55
2021/2022687 29 21 7 62 47 24 26 15 15 50 263 128
2022/20231.016 65 132 31 115 100 149 67 85 97 19 71 85
2023/2024837 13 101 32 45 95 101 82 46 60 89 100 73
2024/20252.045 33 168 93 220 106 109 163 177 326 168 265 217
2025/2026533 288 222 23 0 0 0 0 0 0 0 0 0
Totale 7.265