PORTO @ Archivio Istituzionale della Ricerca

BONIFETTO, ROBERTO
 Distribuzione geografica
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Continente #
NA - Nord America 14.570
EU - Europa 12.093
AS - Asia 8.469
SA - Sud America 703
AF - Africa 287
OC - Oceania 24
Continente sconosciuto - Info sul continente non disponibili 3
Totale 36.149
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Nazione #
US - Stati Uniti d'America 14.389
IT - Italia 4.568
SG - Singapore 2.339
CN - Cina 2.019
VN - Vietnam 1.970
DE - Germania 1.669
FR - Francia 1.355
GB - Regno Unito 1.277
RU - Federazione Russa 1.068
KR - Corea 566
BR - Brasile 563
HK - Hong Kong 435
UA - Ucraina 435
IN - India 251
NL - Olanda 242
FI - Finlandia 228
IE - Irlanda 220
TR - Turchia 213
CH - Svizzera 181
BE - Belgio 163
AT - Austria 152
JP - Giappone 152
CI - Costa d'Avorio 138
SE - Svezia 127
CA - Canada 111
ES - Italia 78
ID - Indonesia 67
AR - Argentina 57
PH - Filippine 55
BG - Bulgaria 53
TH - Thailandia 47
MX - Messico 46
MY - Malesia 45
TW - Taiwan 40
BD - Bangladesh 38
IQ - Iraq 37
GR - Grecia 36
RO - Romania 36
PL - Polonia 34
PT - Portogallo 34
IR - Iran 33
JO - Giordania 31
IL - Israele 25
MA - Marocco 25
HR - Croazia 22
ZA - Sudafrica 21
AU - Australia 20
EC - Ecuador 20
EU - Europa 19
SN - Senegal 19
CZ - Repubblica Ceca 17
SA - Arabia Saudita 17
TG - Togo 17
CO - Colombia 16
AE - Emirati Arabi Uniti 15
CL - Cile 15
KE - Kenya 14
PK - Pakistan 14
PY - Paraguay 14
UZ - Uzbekistan 13
EG - Egitto 10
KZ - Kazakistan 10
LT - Lituania 10
NG - Nigeria 10
AZ - Azerbaigian 9
TN - Tunisia 9
VE - Venezuela 9
EE - Estonia 8
NO - Norvegia 8
SI - Slovenia 8
DK - Danimarca 6
DO - Repubblica Dominicana 6
MD - Moldavia 6
AL - Albania 5
BY - Bielorussia 5
DZ - Algeria 5
HU - Ungheria 5
TT - Trinidad e Tobago 5
ET - Etiopia 4
GE - Georgia 4
JM - Giamaica 4
LV - Lettonia 4
MU - Mauritius 4
NP - Nepal 4
PS - Palestinian Territory 4
UY - Uruguay 4
AP - ???statistics.table.value.countryCode.AP??? 3
BH - Bahrain 3
CR - Costa Rica 3
LB - Libano 3
NZ - Nuova Zelanda 3
OM - Oman 3
RS - Serbia 3
SK - Slovacchia (Repubblica Slovacca) 3
ZW - Zimbabwe 3
A2 - ???statistics.table.value.countryCode.A2??? 2
BO - Bolivia 2
GH - Ghana 2
GY - Guiana 2
LA - Repubblica Popolare Democratica del Laos 2
Totale 36.124
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Città #
Ashburn 2.664
Singapore 1.414
Turin 1.176
Southend 991
Seattle 859
Fairfield 838
Chandler 593
Council Bluffs 589
San Jose 583
Dallas 573
Ho Chi Minh City 507
Torino 478
Hanoi 464
Woodbridge 395
Beijing 386
Houston 368
Cambridge 354
Hong Kong 352
Wilmington 319
Princeton 308
Santa Clara 301
Ann Arbor 286
Milan 265
Hefei 241
Seoul 236
Jacksonville 222
San Ramon 212
Dublin 207
Boardman 196
Berlin 186
Zhengzhou 183
Rome 182
Los Angeles 176
San Mauro Torinese 168
Izmir 161
Abidjan 138
Bern 135
Brussels 135
Shanghai 130
San Donato Milanese 129
Lappeenranta 114
Lauterbourg 114
Saint Petersburg 112
North Bergen 100
Vienna 92
Shenzhen 86
Guangzhou 85
Helsinki 83
Da Nang 81
New York 78
Munich 76
Haiphong 69
Moscow 66
Buffalo 65
Chicago 62
San Francisco 60
Columbus 56
Sofia 53
Jakarta 52
Tokyo 52
Zaporozhye 51
Mountain View 50
The Dalles 50
Paris 49
Baltimore 48
São Paulo 47
Falls Church 46
San Antonio 46
San Diego 46
Frankfurt am Main 43
Dearborn 40
Amsterdam 37
Nuremberg 37
Des Moines 36
Bologna 33
Valfenera 33
Groningen 32
Hangzhou 32
Pennsylvania Furnace 32
Washington 32
London 31
Bremen 28
Genoa 28
Hải Dương 28
Redwood City 28
Toronto 28
Aix-en-provence 27
Frascati 27
Frankfurt 26
Istanbul 26
Varese 25
Nanjing 24
Turku 24
Biên Hòa 23
Borgosesia 23
Chennai 23
Barcelona 22
Cupertino 22
Galati 22
Warsaw 22
Totale 20.983
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Nome #
Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient 688
3D thermal-hydraulic analysis of two irregular field joints for the ITER vacuum vessel 618
4C Code Analysis of High-Margin Quench Propagation in a DEMO TF Coil 581
Design and optimization of Artificial Neural Networks for the modelling of superconducting magnets operation in tokamak fusion reactors 539
DTT - Divertor Tokamak Test facility - Interim Design Report 528
3D thermal-hydraulic analysis of an ITER vacuum vessel regular Field Joint 525
Development of a Thermal-Hydraulic Model for the European DEMO TF Coil 507
Divertor Tokamak Test facility project: status of design and implementation 506
Effects of RANS-Type turbulence models on the convective heat loss computed by CFD in the solar two power tower 496
4C code analysis of thermal-hydraulic transients in the KSTAR PF1 superconducting coil 495
Artificial Neural Network (ANN) modeling of the pulsed heat load during ITER CS magnet operation 463
CFD analysis of a regular sector of the ITER vacuum vessel. Part I: Flow distribution and pressure drop 444
A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors 440
4C code simulation and benchmark of ITER TF magnet cool-down from 300 K to 80 K 439
Quench propagation in a TF coil of the EU DEMO 439
Artificial neural network model for the thermal-hydraulic response of a TF superconducting magnet in ITER 438
CFD analysis of the ITER first wall 06 panel. Part II: Thermal-hydraulics 428
Validation of the 4C code against data from the HELIOS loop at CEA Grenoble 415
Analysis of the DC performance of the ITER CSI coil using the 4C code 413
Incorporating Artificial Neural Networks in the dynamic thermal-hydraulic model of a controlled cryogenic circuit 406
Artificial Neural Networks: a viable tool to design heat load smoothing strategies for the ITER Toroidal Field coils 406
PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS 405
Computational thermal-hydraulic modeling for nuclear fusion and fission applications 402
Mitigation of the Temperature Margin Reduction due to the Nuclear Radiation on the ITER TF Coils 401
Overview of the hydraulic characteristics of the ITER Central Solenoid Model Coil conductors after 15 years of test campaigns 401
Modeling of pulsed heat load in a cryogenic SHe loop using Artificial Neural Networks 395
Thermal-hydraulic analysis of transients in the HELIOS loop including a CICC section representative of the JT-60SA Central Solenoid 395
DTT device: Conceptual design of the superconducting magnet system 392
Prediction, experimental results and analysis of the ITER TF insert coil quench propagation tests, using the 4C code 392
Mechanical analysis of the ENEA TF coil proposal for the EU DEMO fusion reactor 390
Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data 386
Analysis of the cooldown of the ITER central solenoid model coil and insert coil 385
Computation of JT-60SA TF coil temperature margin using the 4C code 380
Analysis of the Effects of the Nuclear Heat Load on the ITER TF Magnets Temperature Margin 379
Performance analysis of a graded winding pack design for the EU DEMO TF coil in normal and off-normal conditions 376
Analysis of AC Losses in the ITER Central Solenoid Insert Coil 375
Verification of the Predictive Capabilities of the 4C Code Cryogenic Circuit Model 368
Analyses of low- and high-margin Quench Propagation in the European DEMO TF Coil Winding Pack 364
Thermal-hydraulic modeling of a novel HTS CICC for nuclear fusion applications 364
Validation of the 4C Thermal-Hydraulic Code against 25 kA Safety Discharge in the ITERToroidal Field Model Coil (TFMC) 363
Numerical analysis of propagation of thermal disturbances in brass-stabilized REBCO tapes 360
Analysis of a protected Loss Of Flow Accident (LOFA) in the ITER TF coil cooling circuit 357
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors 349
CFD analysis of the ITER first wall 06 panel. Part I: Model set-up andflow distribution 341
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 339
Overview of Progress on the EU DEMO Reactor Magnet System Design 336
Modeling of W7-X superconducting coil cool-down using the 4C code 332
4C modeling of pulsed-load smoothing in the HELIOS facility using a controlled bypass valve 328
Analysis of Quench Propagation in the ITER Poloidal Field Conductor Insert (PFCI) 327
4C modeling of the supercritical helium loop HELIOS in isobaric configuration 326
ITER Central Solenoid Insert Test Results 317
DTT vacuum vessel, in-vessel coils, and out vessel systems: overview of design and procurement. 303
Analysis of AC losses in the EAST superconducting magnets using the 4C code 303
Dynamic modeling of a Supercritical Helium closed loop with the 4C code 302
Application of the 4C code to the thermal-hydraulic analysis of the CS superconducting magnets in EAST 301
Analysis of Quench Propagation in the ITER Central Solenoid Insert (CSI) Coil 301
Cutting-edge R&D activities of CIRTEN in support of the Technology Park annexed to the Italian National Repository of radioactive waste 300
Full-core coupled neutronic/thermal-hydraulic modelling of GEN-IV LMFBRs 300
Performance analysis of the NbTi PF coils for the EU DEMO fusion reactor 286
Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code 283
Parametric analysis of the ITER TF fast discharge using the 4C code 276
Modelling the PbLi flow including tritium transport and permeation with GETTHEM 274
Improved Conceptual Design of the Beamline for the DTT Neutral Beam Injector 272
Analysis of a Loss-of-Flow Accident (LOFA) in a tokamak superconducting toroidal field coil 271
Analysis of the thermal-hydraulic effects of a plasma disruption on the DTT TF magnets 270
Thermal-Hydraulic Code-to-Code Benchmark in a Simplified EBR-II Geometry 269
Thermal-Hydraulic Simulation of 80 kA Safety Discharge in the ITER Toroidal Field Model Coil (TFMC) using the 4C Code 267
Metamodeling and on-line clustering for loss-of-flow accident precursors identification in a superconducting magnet cryogenic cooling circuit 266
DTT: A Challenging Framework for a Sound Superconducting Magnets Design 265
Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO 264
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS 263
Design and Integration of the WCLL Tritium Extraction and Removal System into the European DEMO Tokamak Reactor 260
Innovative concepts in the DTT neutral beam injector 257
Self Consistent Electrical and Thermal-Hydraulic Model of Faults in Superconducting Magnets: EU DEMO TF Short Circuit During a Fast Discharge 256
Advanced methods for loss-of-flow accident precursors identification in a superconducting magnet cryogenic cooling circuit 256
Engineering design of a Permeator Against Vacuum mock-up with niobium membrane 255
The DEMO magnet system – Status and future challenges 252
First Validation of the FRENETIC Code Thermal-Hydraulic Model against the ENEA Integral Circulation Experiment 244
Characterization of the ITER CS conductor and projection to the ITER CS performance 242
Computational Thermal-Fluid Dynamics analyses of borated water distribution in the Vacuum Vessel of the Divertor Tokamak Test facility 238
Development of an integrated thermo-mechanical simulation environment for quench analyses in HTS cables for fusion 234
Design of the cryogenic loop for the superconducting toroidal-field magnets of the Divertor Tokamak Test 229
Modeling Quench Propagation in the ENEA HTS Cable-In-Conduit Conductor 218
Identification of LOFA precursors in ITER superconducting magnet cryogenic cooling circuit 216
Innovative Concepts in the Design of DTT Neutral Beam Injector. 215
Thermal-hydraulic and mechanical analysis of the Beam Line Components for the DTT Neutral Beam Injector 213
Analysis of the ITER central solenoid insert (CSI) coil stability tests 212
Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption 208
Integrated design strategy for EU-DEMO first wall protection from plasma transients 208
Validation of the 4C Code on the AC Loss Tests of a Full-Scale ITER Coil 205
Application of the Polynomial Chaos Expansion to the Uncertainty Propagation in Fault Transients in Nuclear Fusion Reactors: DTT TF Fast Current Discharge 192
Integrated deterministic and probabilistic safety assessment of a superconducting magnet cryogenic cooling circuit for nuclear fusion applications 188
Testing of the ITER CS Module #4 187
Coupling and Hysteresis Loss Measurements on the ITER CS Module #4 183
Thermal-hydraulic test and analysis of the ENEA TF conductor sample for the EU DEMO fusion reactor 179
Advance in the conceptual design of the European DEMO magnet system 179
DTT toroidal field conductor samples test in Sultan: DC and AC characterization 179
Quench experiments on sub-size HTS Cable-In-Conduit Conductors for fusion applications: Data analysis and model validation 177
Engineering design of the thermal shield for the Divertor Tokamak Test (DTT) facility 176
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)) 172
Totale 33.105
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Categoria #
all - tutte 87.949
article - articoli 70.223
book - libri 1.045
conference - conferenze 15.195
curatela - curatele 0
other - altro 634
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 175.046
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021415 0 0 0 0 0 0 0 0 0 208 102 105
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
2025/20269.880 737 662 985 807 755 653 1.420 767 2.163 931 0 0
Totale 36.583