PORTO @ Archivio Istituzionale della Ricerca

BONIFETTO, ROBERTO
 Distribuzione geografica
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Continente #
NA - Nord America 12.933
EU - Europa 10.867
AS - Asia 4.072
SA - Sud America 487
AF - Africa 224
OC - Oceania 18
Continente sconosciuto - Info sul continente non disponibili 3
Totale 28.604
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Nazione #
US - Stati Uniti d'America 12.810
IT - Italia 4.347
CN - Cina 1.766
DE - Germania 1.603
GB - Regno Unito 1.241
FR - Francia 1.207
SG - Singapore 1.023
RU - Federazione Russa 461
UA - Ucraina 431
BR - Brasile 430
KR - Corea 420
IE - Irlanda 217
FI - Finlandia 209
TR - Turchia 204
NL - Olanda 194
HK - Hong Kong 181
CH - Svizzera 177
BE - Belgio 161
AT - Austria 148
CI - Costa d'Avorio 136
SE - Svezia 124
JP - Giappone 91
CA - Canada 90
IN - India 84
ES - Italia 64
VN - Vietnam 62
ID - Indonesia 60
BG - Bulgaria 53
RO - Romania 35
GR - Grecia 32
IR - Iran 31
MX - Messico 27
JO - Giordania 24
PL - Polonia 24
AR - Argentina 23
IL - Israele 22
HR - Croazia 21
PT - Portogallo 21
EU - Europa 19
MY - Malesia 19
SN - Senegal 17
TG - Togo 17
CZ - Repubblica Ceca 16
AU - Australia 15
BD - Bangladesh 12
EC - Ecuador 11
AE - Emirati Arabi Uniti 10
NG - Nigeria 9
TW - Taiwan 9
NO - Norvegia 8
SA - Arabia Saudita 8
SI - Slovenia 8
CL - Cile 7
EE - Estonia 7
EG - Egitto 7
LT - Lituania 7
UZ - Uzbekistan 7
ZA - Sudafrica 7
CO - Colombia 6
IQ - Iraq 6
PH - Filippine 6
DK - Danimarca 5
DZ - Algeria 5
KE - Kenya 5
MA - Marocco 5
MD - Moldavia 5
PK - Pakistan 5
PY - Paraguay 5
TN - Tunisia 5
KZ - Kazakistan 4
LV - Lettonia 4
AP - ???statistics.table.value.countryCode.AP??? 3
AZ - Azerbaigian 3
JM - Giamaica 3
MU - Mauritius 3
RS - Serbia 3
VE - Venezuela 3
ZW - Zimbabwe 3
A2 - ???statistics.table.value.countryCode.A2??? 2
BH - Bahrain 2
BY - Bielorussia 2
GE - Georgia 2
GH - Ghana 2
HU - Ungheria 2
LA - Repubblica Popolare Democratica del Laos 2
LU - Lussemburgo 2
NP - Nepal 2
NZ - Nuova Zelanda 2
OM - Oman 2
PS - Palestinian Territory 2
SK - Slovacchia (Repubblica Slovacca) 2
TH - Thailandia 2
AL - Albania 1
AM - Armenia 1
BO - Bolivia 1
BW - Botswana 1
DO - Repubblica Dominicana 1
GA - Gabon 1
GN - Guinea 1
KG - Kirghizistan 1
Totale 28.597
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Città #
Ashburn 2.450
Turin 1.121
Southend 991
Seattle 858
Fairfield 838
Singapore 608
Chandler 593
Council Bluffs 564
Dallas 531
Torino 478
Woodbridge 395
Houston 364
Cambridge 354
Beijing 348
Wilmington 318
Princeton 308
Ann Arbor 286
Santa Clara 259
Milan 234
Jacksonville 222
Hefei 214
San Ramon 212
Dublin 204
Boardman 194
Berlin 186
Zhengzhou 183
San Mauro Torinese 168
Izmir 161
Hong Kong 142
Rome 141
Abidjan 136
Bern 135
Brussels 134
Seoul 131
San Donato Milanese 129
Shanghai 123
Saint Petersburg 112
Lappeenranta 106
Vienna 90
Shenzhen 82
Guangzhou 81
Helsinki 78
Munich 63
Los Angeles 60
Chicago 59
San Francisco 56
Buffalo 54
Sofia 53
Jakarta 51
Zaporozhye 51
Mountain View 50
Baltimore 48
Falls Church 46
San Antonio 46
New York 45
San Diego 43
Columbus 41
Paris 41
Dearborn 40
The Dalles 40
Des Moines 36
Nuremberg 34
São Paulo 34
Valfenera 33
Pennsylvania Furnace 32
Washington 32
Amsterdam 29
Hangzhou 29
Bremen 28
Redwood City 28
Toronto 28
Aix-en-provence 27
Bologna 27
Frascati 27
Genoa 27
Frankfurt 26
London 25
Varese 25
Istanbul 24
Nanjing 24
Borgosesia 23
Cupertino 22
Galati 22
Chengdu 21
Hanoi 21
Montréal 21
Turku 21
Barcelona 20
Fremont 20
Naaldwijk 20
Zagreb 20
Norwalk 19
Redmond 19
Yubileyny 19
Atlanta 18
Genova 18
Indiana 18
Osaka 18
Boston 17
Lansing 17
Totale 17.118
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Nome #
Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient 625
3D thermal-hydraulic analysis of two irregular field joints for the ITER vacuum vessel 586
4C Code Analysis of High-Margin Quench Propagation in a DEMO TF Coil 529
Design and optimization of Artificial Neural Networks for the modelling of superconducting magnets operation in tokamak fusion reactors 478
3D thermal-hydraulic analysis of an ITER vacuum vessel regular Field Joint 474
4C code analysis of thermal-hydraulic transients in the KSTAR PF1 superconducting coil 462
Effects of RANS-Type turbulence models on the convective heat loss computed by CFD in the solar two power tower 455
Development of a Thermal-Hydraulic Model for the European DEMO TF Coil 438
DTT - Divertor Tokamak Test facility - Interim Design Report 430
Artificial Neural Network (ANN) modeling of the pulsed heat load during ITER CS magnet operation 417
4C code simulation and benchmark of ITER TF magnet cool-down from 300 K to 80 K 406
CFD analysis of the ITER first wall 06 panel. Part II: Thermal-hydraulics 401
Artificial neural network model for the thermal-hydraulic response of a TF superconducting magnet in ITER 399
A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors 398
CFD analysis of a regular sector of the ITER vacuum vessel. Part I: Flow distribution and pressure drop 391
Analysis of the DC performance of the ITER CSI coil using the 4C code 378
PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS 378
Quench propagation in a TF coil of the EU DEMO 376
Mitigation of the Temperature Margin Reduction due to the Nuclear Radiation on the ITER TF Coils 361
Validation of the 4C code against data from the HELIOS loop at CEA Grenoble 361
Artificial Neural Networks: a viable tool to design heat load smoothing strategies for the ITER Toroidal Field coils 353
Overview of the hydraulic characteristics of the ITER Central Solenoid Model Coil conductors after 15 years of test campaigns 352
Modeling of pulsed heat load in a cryogenic SHe loop using Artificial Neural Networks 348
Prediction, experimental results and analysis of the ITER TF insert coil quench propagation tests, using the 4C code 347
Mechanical analysis of the ENEA TF coil proposal for the EU DEMO fusion reactor 347
Incorporating Artificial Neural Networks in the dynamic thermal-hydraulic model of a controlled cryogenic circuit 343
DTT device: Conceptual design of the superconducting magnet system 340
Analysis of the Effects of the Nuclear Heat Load on the ITER TF Magnets Temperature Margin 338
Thermal-hydraulic analysis of transients in the HELIOS loop including a CICC section representative of the JT-60SA Central Solenoid 338
Divertor Tokamak Test facility project: status of design and implementation 337
Computation of JT-60SA TF coil temperature margin using the 4C code 337
Performance analysis of a graded winding pack design for the EU DEMO TF coil in normal and off-normal conditions 336
Analysis of the cooldown of the ITER central solenoid model coil and insert coil 333
Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data 330
Analyses of low- and high-margin Quench Propagation in the European DEMO TF Coil Winding Pack 324
Computational thermal-hydraulic modeling for nuclear fusion and fission applications 323
Verification of the Predictive Capabilities of the 4C Code Cryogenic Circuit Model 318
Thermal-hydraulic modeling of a novel HTS CICC for nuclear fusion applications 315
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors 311
Analysis of a protected Loss Of Flow Accident (LOFA) in the ITER TF coil cooling circuit 305
Validation of the 4C Thermal-Hydraulic Code against 25 kA Safety Discharge in the ITERToroidal Field Model Coil (TFMC) 305
Numerical analysis of propagation of thermal disturbances in brass-stabilized REBCO tapes 304
CFD analysis of the ITER first wall 06 panel. Part I: Model set-up andflow distribution 302
Modeling of W7-X superconducting coil cool-down using the 4C code 302
4C modeling of the supercritical helium loop HELIOS in isobaric configuration 300
Analysis of AC Losses in the ITER Central Solenoid Insert Coil 299
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 296
Overview of Progress on the EU DEMO Reactor Magnet System Design 295
Analysis of Quench Propagation in the ITER Poloidal Field Conductor Insert (PFCI) 293
ITER Central Solenoid Insert Test Results 291
4C modeling of pulsed-load smoothing in the HELIOS facility using a controlled bypass valve 288
Dynamic modeling of a Supercritical Helium closed loop with the 4C code 279
Application of the 4C code to the thermal-hydraulic analysis of the CS superconducting magnets in EAST 268
Analysis of AC losses in the EAST superconducting magnets using the 4C code 267
Analysis of Quench Propagation in the ITER Central Solenoid Insert (CSI) Coil 262
Full-core coupled neutronic/thermal-hydraulic modelling of GEN-IV LMFBRs 255
Thermal-Hydraulic Simulation of 80 kA Safety Discharge in the ITER Toroidal Field Model Coil (TFMC) using the 4C Code 250
Parametric analysis of the ITER TF fast discharge using the 4C code 244
Performance analysis of the NbTi PF coils for the EU DEMO fusion reactor 231
Thermal-Hydraulic Code-to-Code Benchmark in a Simplified EBR-II Geometry 230
Analysis of a Loss-of-Flow Accident (LOFA) in a tokamak superconducting toroidal field coil 229
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS 216
First Validation of the FRENETIC Code Thermal-Hydraulic Model against the ENEA Integral Circulation Experiment 207
Characterization of the ITER CS conductor and projection to the ITER CS performance 207
The DEMO magnet system – Status and future challenges 203
DTT: A Challenging Framework for a Sound Superconducting Magnets Design 199
Engineering design of a Permeator Against Vacuum mock-up with niobium membrane 196
Improved Conceptual Design of the Beamline for the DTT Neutral Beam Injector 185
Cutting-edge R&D activities of CIRTEN in support of the Technology Park annexed to the Italian National Repository of radioactive waste 185
Metamodeling and on-line clustering for loss-of-flow accident precursors identification in a superconducting magnet cryogenic cooling circuit 176
Analysis of the ITER central solenoid insert (CSI) coil stability tests 175
Modeling Quench Propagation in the ENEA HTS Cable-In-Conduit Conductor 174
Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code 168
DTT vacuum vessel, in-vessel coils, and out vessel systems: overview of design and procurement. 155
Self Consistent Electrical and Thermal-Hydraulic Model of Faults in Superconducting Magnets: EU DEMO TF Short Circuit During a Fast Discharge 151
Integrated design strategy for EU-DEMO first wall protection from plasma transients 149
Thermal-hydraulic and mechanical analysis of the Beam Line Components for the DTT Neutral Beam Injector 148
Thermal-hydraulic test and analysis of the ENEA TF conductor sample for the EU DEMO fusion reactor 146
Analysis of the thermal-hydraulic effects of a plasma disruption on the DTT TF magnets 145
Advanced methods for loss-of-flow accident precursors identification in a superconducting magnet cryogenic cooling circuit 144
Design and Integration of the WCLL Tritium Extraction and Removal System into the European DEMO Tokamak Reactor 143
Innovative concepts in the DTT neutral beam injector 141
Identification of LOFA precursors in ITER superconducting magnet cryogenic cooling circuit 140
Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO 138
Validation of the 4C Code on the AC Loss Tests of a Full-Scale ITER Coil 137
Modelling the PbLi flow including tritium transport and permeation with GETTHEM 133
AC Losses in the First ITER CS Module Tests: Experimental Results and Comparison to Analytical Models 131
AC Losses in the Second Module of the ITER Central Solenoid 128
Integrated deterministic and probabilistic safety assessment of a superconducting magnet cryogenic cooling circuit for nuclear fusion applications 126
Development of an integrated thermo-mechanical simulation environment for quench analyses in HTS cables for fusion 125
Design of the cryogenic loop for the superconducting toroidal-field magnets of the Divertor Tokamak Test 124
Thermal-hydraulic analysis of the DTT Toroidal Field magnets in DC operation 122
Erratum: Integrated design strategy for EU-DEMO first wall protection from plasma transients (Fusion Engineering and Design (2022) 177, (113067) (S0920379622000679), (10.1016/j.fusengdes.2022.113067)) 122
Computational Thermal-Fluid Dynamics analyses of borated water distribution in the Vacuum Vessel of the Divertor Tokamak Test facility 121
3D-FOX—A 3D Transient Electromagnetic Code for Eddy Currents Computation in Superconducting Magnet Structures: DTT TF Fast Current Discharge Analysis 119
Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption 118
Progress in the design of the superconducting magnets for the EU DEMO 118
Application of the Polynomial Chaos Expansion to the Uncertainty Propagation in Fault Transients in Nuclear Fusion Reactors: DTT TF Fast Current Discharge 116
Development of the H4C Model of Quench Propagation in the ENEA HTS Cable-In-Conduit Conductor 114
Advance in the conceptual design of the European DEMO magnet system 113
Totale 27.066
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Categoria #
all - tutte 74.232
article - articoli 59.407
book - libri 857
conference - conferenze 12.730
curatela - curatele 0
other - altro 504
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 147.730
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/20211.237 0 0 72 193 114 122 102 117 102 208 102 105
2021/20221.600 80 106 41 99 50 137 95 34 60 167 405 326
2022/20232.392 237 370 73 250 219 312 164 168 201 21 153 224
2023/20241.575 33 315 48 83 118 129 102 80 111 187 144 225
2024/20255.355 100 519 371 605 370 351 385 350 628 504 682 490
2025/20262.318 737 662 919 0 0 0 0 0 0 0 0 0
Totale 29.021