PORTO @ Archivio Istituzionale della Ricerca

BONIFETTO, ROBERTO
 Distribuzione geografica
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Continente #
NA - Nord America 15.103
EU - Europa 12.599
AS - Asia 8.692
SA - Sud America 710
AF - Africa 289
OC - Oceania 24
Continente sconosciuto - Info sul continente non disponibili 3
Totale 37.420
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Nazione #
US - Stati Uniti d'America 14.893
IT - Italia 5.055
SG - Singapore 2.397
CN - Cina 2.042
VN - Vietnam 1.970
DE - Germania 1.670
FR - Francia 1.356
GB - Regno Unito 1.280
RU - Federazione Russa 1.068
KR - Corea 568
BR - Brasile 564
HK - Hong Kong 442
UA - Ucraina 435
IN - India 253
NL - Olanda 246
FI - Finlandia 228
IE - Irlanda 220
TR - Turchia 213
CH - Svizzera 187
BD - Bangladesh 166
BE - Belgio 164
JP - Giappone 153
AT - Austria 152
CI - Costa d'Avorio 138
CA - Canada 132
SE - Svezia 127
ES - Italia 79
ID - Indonesia 67
AR - Argentina 58
PH - Filippine 55
BG - Bulgaria 53
MX - Messico 47
TH - Thailandia 47
MY - Malesia 45
TW - Taiwan 40
IQ - Iraq 37
GR - Grecia 36
RO - Romania 36
PL - Polonia 34
PT - Portogallo 34
IR - Iran 33
JO - Giordania 32
MA - Marocco 27
IL - Israele 25
HR - Croazia 23
EC - Ecuador 21
ZA - Sudafrica 21
AU - Australia 20
EU - Europa 19
SN - Senegal 19
CL - Cile 17
CO - Colombia 17
CZ - Repubblica Ceca 17
SA - Arabia Saudita 17
TG - Togo 17
AE - Emirati Arabi Uniti 16
KE - Kenya 14
PK - Pakistan 14
PY - Paraguay 14
UZ - Uzbekistan 13
LT - Lituania 11
EG - Egitto 10
KZ - Kazakistan 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
JM - Giamaica 6
MD - Moldavia 6
TT - Trinidad e Tobago 6
AL - Albania 5
BY - Bielorussia 5
DZ - Algeria 5
HU - Ungheria 5
UY - Uruguay 5
ET - Etiopia 4
GE - Georgia 4
LV - Lettonia 4
MU - Mauritius 4
NP - Nepal 4
PS - Palestinian Territory 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
BB - Barbados 2
BO - Bolivia 2
GH - Ghana 2
GY - Guiana 2
Totale 37.391
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Città #
Ashburn 2.735
Singapore 1.425
Turin 1.212
Southend 991
Seattle 859
Fairfield 838
San Jose 742
Council Bluffs 624
Chandler 593
Dallas 576
Ho Chi Minh City 507
Torino 478
Hanoi 464
Milan 410
Woodbridge 395
Beijing 389
Houston 370
Cambridge 357
Hong Kong 357
Wilmington 319
Santa Clara 318
Princeton 308
Ann Arbor 286
Rome 276
Hefei 241
Seoul 238
Jacksonville 222
Boardman 218
San Ramon 212
Dublin 207
Los Angeles 191
Berlin 186
Zhengzhou 183
San Mauro Torinese 168
Izmir 161
Abidjan 138
Brussels 136
Bern 135
Shanghai 131
San Donato Milanese 129
Lappeenranta 114
Lauterbourg 114
Saint Petersburg 112
New York 106
North Bergen 100
Vienna 92
Shenzhen 86
Guangzhou 85
Helsinki 83
Da Nang 81
Buffalo 76
Munich 76
Haiphong 69
Moscow 66
Chicago 65
San Francisco 62
Columbus 61
Sofia 53
Tokyo 53
Jakarta 52
Zaporozhye 51
Mountain View 50
Paris 50
The Dalles 50
Baltimore 48
São Paulo 47
Falls Church 46
San Antonio 46
San Diego 46
Frankfurt am Main 43
Dearborn 40
Bologna 38
Amsterdam 37
Nuremberg 37
Des Moines 36
Valfenera 33
Figino 32
Groningen 32
Hangzhou 32
Pennsylvania Furnace 32
Washington 32
Genoa 31
London 31
Toronto 31
Naples 29
Bremen 28
Hải Dương 28
Redwood City 28
Aix-en-provence 27
Frascati 27
Frankfurt 26
Istanbul 26
Montreal 26
Nanjing 25
Varese 25
Turku 24
Barcelona 23
Bari 23
Biên Hòa 23
Borgosesia 23
Totale 21.693
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Nome #
Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient 692
3D thermal-hydraulic analysis of two irregular field joints for the ITER vacuum vessel 622
4C Code Analysis of High-Margin Quench Propagation in a DEMO TF Coil 583
Divertor Tokamak Test facility project: status of design and implementation 555
DTT - Divertor Tokamak Test facility - Interim Design Report 550
Design and optimization of Artificial Neural Networks for the modelling of superconducting magnets operation in tokamak fusion reactors 548
3D thermal-hydraulic analysis of an ITER vacuum vessel regular Field Joint 529
Development of a Thermal-Hydraulic Model for the European DEMO TF Coil 514
Effects of RANS-Type turbulence models on the convective heat loss computed by CFD in the solar two power tower 499
4C code analysis of thermal-hydraulic transients in the KSTAR PF1 superconducting coil 498
Artificial Neural Network (ANN) modeling of the pulsed heat load during ITER CS magnet operation 465
CFD analysis of a regular sector of the ITER vacuum vessel. Part I: Flow distribution and pressure drop 449
A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors 445
Quench propagation in a TF coil of the EU DEMO 443
4C code simulation and benchmark of ITER TF magnet cool-down from 300 K to 80 K 442
Artificial neural network model for the thermal-hydraulic response of a TF superconducting magnet in ITER 442
CFD analysis of the ITER first wall 06 panel. Part II: Thermal-hydraulics 430
Validation of the 4C code against data from the HELIOS loop at CEA Grenoble 420
Artificial Neural Networks: a viable tool to design heat load smoothing strategies for the ITER Toroidal Field coils 417
Analysis of the DC performance of the ITER CSI coil using the 4C code 417
Mitigation of the Temperature Margin Reduction due to the Nuclear Radiation on the ITER TF Coils 415
Incorporating Artificial Neural Networks in the dynamic thermal-hydraulic model of a controlled cryogenic circuit 414
DTT device: Conceptual design of the superconducting magnet system 413
Computational thermal-hydraulic modeling for nuclear fusion and fission applications 407
Modeling of pulsed heat load in a cryogenic SHe loop using Artificial Neural Networks 406
PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS 406
Overview of the hydraulic characteristics of the ITER Central Solenoid Model Coil conductors after 15 years of test campaigns 404
Prediction, experimental results and analysis of the ITER TF insert coil quench propagation tests, using the 4C code 401
Thermal-hydraulic analysis of transients in the HELIOS loop including a CICC section representative of the JT-60SA Central Solenoid 398
Mechanical analysis of the ENEA TF coil proposal for the EU DEMO fusion reactor 394
Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data 390
Analysis of the cooldown of the ITER central solenoid model coil and insert coil 388
Thermal-hydraulic modeling of a novel HTS CICC for nuclear fusion applications 386
Analysis of the Effects of the Nuclear Heat Load on the ITER TF Magnets Temperature Margin 383
Performance analysis of a graded winding pack design for the EU DEMO TF coil in normal and off-normal conditions 382
Computation of JT-60SA TF coil temperature margin using the 4C code 381
Analysis of AC Losses in the ITER Central Solenoid Insert Coil 378
Verification of the Predictive Capabilities of the 4C Code Cryogenic Circuit Model 372
Numerical analysis of propagation of thermal disturbances in brass-stabilized REBCO tapes 368
Validation of the 4C Thermal-Hydraulic Code against 25 kA Safety Discharge in the ITERToroidal Field Model Coil (TFMC) 366
Analyses of low- and high-margin Quench Propagation in the European DEMO TF Coil Winding Pack 365
Analysis of a protected Loss Of Flow Accident (LOFA) in the ITER TF coil cooling circuit 364
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors 353
CFD analysis of the ITER first wall 06 panel. Part I: Model set-up andflow distribution 344
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 343
DTT vacuum vessel, in-vessel coils, and out vessel systems: overview of design and procurement. 341
Overview of Progress on the EU DEMO Reactor Magnet System Design 339
Modeling of W7-X superconducting coil cool-down using the 4C code 333
Cutting-edge R&D activities of CIRTEN in support of the Technology Park annexed to the Italian National Repository of radioactive waste 330
4C modeling of pulsed-load smoothing in the HELIOS facility using a controlled bypass valve 330
Analysis of Quench Propagation in the ITER Poloidal Field Conductor Insert (PFCI) 329
4C modeling of the supercritical helium loop HELIOS in isobaric configuration 327
ITER Central Solenoid Insert Test Results 321
Dynamic modeling of a Supercritical Helium closed loop with the 4C code 308
Analysis of AC losses in the EAST superconducting magnets using the 4C code 307
Analysis of Quench Propagation in the ITER Central Solenoid Insert (CSI) Coil 307
Modelling the PbLi flow including tritium transport and permeation with GETTHEM 307
Application of the 4C code to the thermal-hydraulic analysis of the CS superconducting magnets in EAST 302
Full-core coupled neutronic/thermal-hydraulic modelling of GEN-IV LMFBRs 302
Design and Integration of the WCLL Tritium Extraction and Removal System into the European DEMO Tokamak Reactor 295
Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code 295
Performance analysis of the NbTi PF coils for the EU DEMO fusion reactor 287
Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO 286
Parametric analysis of the ITER TF fast discharge using the 4C code 280
Self Consistent Electrical and Thermal-Hydraulic Model of Faults in Superconducting Magnets: EU DEMO TF Short Circuit During a Fast Discharge 279
Improved Conceptual Design of the Beamline for the DTT Neutral Beam Injector 277
Innovative concepts in the DTT neutral beam injector 275
Analysis of a Loss-of-Flow Accident (LOFA) in a tokamak superconducting toroidal field coil 274
DTT: A Challenging Framework for a Sound Superconducting Magnets Design 274
Thermal-Hydraulic Code-to-Code Benchmark in a Simplified EBR-II Geometry 273
Analysis of the thermal-hydraulic effects of a plasma disruption on the DTT TF magnets 273
Computational Thermal-Fluid Dynamics analyses of borated water distribution in the Vacuum Vessel of the Divertor Tokamak Test facility 272
Thermal-Hydraulic Simulation of 80 kA Safety Discharge in the ITER Toroidal Field Model Coil (TFMC) using the 4C Code 272
Metamodeling and on-line clustering for loss-of-flow accident precursors identification in a superconducting magnet cryogenic cooling circuit 270
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS 267
Engineering design of a Permeator Against Vacuum mock-up with niobium membrane 264
Advanced methods for loss-of-flow accident precursors identification in a superconducting magnet cryogenic cooling circuit 261
Design of the cryogenic loop for the superconducting toroidal-field magnets of the Divertor Tokamak Test 258
The DEMO magnet system – Status and future challenges 257
Development of an integrated thermo-mechanical simulation environment for quench analyses in HTS cables for fusion 254
First Validation of the FRENETIC Code Thermal-Hydraulic Model against the ENEA Integral Circulation Experiment 248
Characterization of the ITER CS conductor and projection to the ITER CS performance 244
Testing of the ITER CS Module #4 237
Innovative Concepts in the Design of DTT Neutral Beam Injector. 236
Validation of the 4C Code on the AC Loss Tests of a Full-Scale ITER Coil 230
Modeling Quench Propagation in the ENEA HTS Cable-In-Conduit Conductor 223
Identification of LOFA precursors in ITER superconducting magnet cryogenic cooling circuit 218
Thermal-hydraulic and mechanical analysis of the Beam Line Components for the DTT Neutral Beam Injector 217
Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption 216
Analysis of the ITER central solenoid insert (CSI) coil stability tests 216
Integrated design strategy for EU-DEMO first wall protection from plasma transients 212
Application of the Polynomial Chaos Expansion to the Uncertainty Propagation in Fault Transients in Nuclear Fusion Reactors: DTT TF Fast Current Discharge 209
Coupling and Hysteresis Loss Measurements on the ITER CS Module #4 206
DTT toroidal field conductor samples test in Sultan: DC and AC characterization 197
Engineering design of the thermal shield for the Divertor Tokamak Test (DTT) facility 195
Integrated deterministic and probabilistic safety assessment of a superconducting magnet cryogenic cooling circuit for nuclear fusion applications 192
Progresses in the development of the tritium extraction and removal system for the water-cooled lithium-lead breeding blanket in EUROfusion 191
Quench experiments on sub-size HTS Cable-In-Conduit Conductors for fusion applications: Data analysis and model validation 190
Advance in the conceptual design of the European DEMO magnet system 183
Thermal-hydraulic test and analysis of the ENEA TF conductor sample for the EU DEMO fusion reactor 181
Totale 34.048
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Categoria #
all - tutte 92.530
article - articoli 73.881
book - libri 1.146
conference - conferenze 15.960
curatela - curatele 0
other - altro 660
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 184.177
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021105 0 0 0 0 0 0 0 0 0 0 0 105
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
2025/202611.154 737 662 985 807 755 653 1.420 767 2.163 963 338 904
Totale 37.857