PORTO @ Archivio Istituzionale della Ricerca

BONIFETTO, ROBERTO
 Distribuzione geografica
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Continente #
NA - Nord America 15.746
EU - Europa 12.811
AS - Asia 8.863
SA - Sud America 724
Continente sconosciuto - Info sul continente non disponibili 442
AF - Africa 289
OC - Oceania 24
Totale 38.899
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Nazione #
US - Stati Uniti d'America 15.453
IT - Italia 5.227
SG - Singapore 2.439
CN - Cina 2.049
VN - Vietnam 1.980
DE - Germania 1.679
FR - Francia 1.365
GB - Regno Unito 1.283
RU - Federazione Russa 1.068
KR - Corea 577
BR - Brasile 567
HK - Hong Kong 443
UA - Ucraina 435
IN - India 256
NL - Olanda 249
BD - Bangladesh 247
FI - Finlandia 228
IE - Irlanda 220
TR - Turchia 213
CH - Svizzera 190
BE - Belgio 164
CA - Canada 161
JP - Giappone 160
AT - Austria 152
CI - Costa d'Avorio 138
SE - Svezia 131
ES - Italia 85
ID - Indonesia 68
AR - Argentina 61
PH - Filippine 56
BG - Bulgaria 53
MX - Messico 51
TH - Thailandia 47
MY - Malesia 46
TW - Taiwan 41
IQ - Iraq 37
GR - Grecia 36
RO - Romania 36
PL - Polonia 35
PT - Portogallo 34
IR - Iran 33
JO - Giordania 32
IL - Israele 27
MA - Marocco 27
EC - Ecuador 23
HR - Croazia 23
ZA - Sudafrica 21
AU - Australia 20
CL - Cile 20
CO - Colombia 20
EU - Europa 19
SA - Arabia Saudita 19
SN - Senegal 19
CR - Costa Rica 18
CZ - Repubblica Ceca 18
AE - Emirati Arabi Uniti 17
JM - Giamaica 17
TG - Togo 17
PK - Pakistan 15
KE - Kenya 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
TT - Trinidad e Tobago 7
DK - Danimarca 6
DO - Repubblica Dominicana 6
MD - Moldavia 6
NI - Nicaragua 6
AL - Albania 5
BY - Bielorussia 5
DZ - Algeria 5
GT - Guatemala 5
HU - Ungheria 5
UY - Uruguay 5
ET - Etiopia 4
GE - Georgia 4
LV - Lettonia 4
MU - Mauritius 4
NP - Nepal 4
PR - Porto Rico 4
PS - Palestinian Territory 4
AP - ???statistics.table.value.countryCode.AP??? 3
BH - Bahrain 3
BS - Bahamas 3
LB - Libano 3
NZ - Nuova Zelanda 3
OM - Oman 3
PA - Panama 3
RS - Serbia 3
SK - Slovacchia (Repubblica Slovacca) 3
SV - El Salvador 3
Totale 38.417
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Città #
Ashburn 2.819
Singapore 1.430
Turin 1.237
Southend 991
Seattle 863
Fairfield 838
San Jose 776
Council Bluffs 702
Chandler 593
Dallas 584
Ho Chi Minh City 509
Torino 478
Hanoi 470
Milan 426
Woodbridge 395
Beijing 389
Houston 370
Hong Kong 358
Cambridge 357
Santa Clara 345
Wilmington 320
Princeton 308
Rome 300
Ann Arbor 286
Hefei 241
Seoul 241
Jacksonville 222
Boardman 219
San Ramon 212
Dublin 207
Los Angeles 206
Berlin 186
Zhengzhou 183
San Mauro Torinese 168
Izmir 161
Abidjan 138
Brussels 136
Bern 135
Shanghai 132
San Donato Milanese 129
New York 118
Lappeenranta 114
Lauterbourg 114
Saint Petersburg 112
North Bergen 100
Vienna 92
Shenzhen 86
Guangzhou 85
Buffalo 83
Helsinki 83
Da Nang 81
Chicago 78
Munich 76
Haiphong 69
Moscow 66
San Francisco 65
Columbus 62
Sofia 53
Tokyo 53
Jakarta 52
Paris 52
Zaporozhye 51
Mountain View 50
The Dalles 50
Baltimore 48
San Antonio 47
San Diego 47
São Paulo 47
Falls Church 46
Bologna 44
Frankfurt am Main 43
Dearborn 40
Washington 38
Amsterdam 37
Nuremberg 37
Des Moines 36
Naples 36
Genoa 35
London 34
Valfenera 33
Figino 32
Groningen 32
Hangzhou 32
Pennsylvania Furnace 32
Phoenix 32
Toronto 31
Montreal 29
Atlanta 28
Bremen 28
Hải Dương 28
Redwood City 28
Aix-en-provence 27
Frascati 27
Varese 27
Frankfurt 26
Istanbul 26
Palermo 26
Nanjing 25
Barcelona 24
Bari 24
Totale 22.117
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Nome #
Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient 708
Divertor Tokamak Test facility project: status of design and implementation 627
3D thermal-hydraulic analysis of two irregular field joints for the ITER vacuum vessel 625
4C Code Analysis of High-Margin Quench Propagation in a DEMO TF Coil 589
DTT - Divertor Tokamak Test facility - Interim Design Report 579
Design and optimization of Artificial Neural Networks for the modelling of superconducting magnets operation in tokamak fusion reactors 561
3D thermal-hydraulic analysis of an ITER vacuum vessel regular Field Joint 534
Development of a Thermal-Hydraulic Model for the European DEMO TF Coil 519
4C code analysis of thermal-hydraulic transients in the KSTAR PF1 superconducting coil 505
Effects of RANS-Type turbulence models on the convective heat loss computed by CFD in the solar two power tower 502
Artificial Neural Network (ANN) modeling of the pulsed heat load during ITER CS magnet operation 470
CFD analysis of a regular sector of the ITER vacuum vessel. Part I: Flow distribution and pressure drop 457
A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors 450
4C code simulation and benchmark of ITER TF magnet cool-down from 300 K to 80 K 448
Quench propagation in a TF coil of the EU DEMO 448
Artificial neural network model for the thermal-hydraulic response of a TF superconducting magnet in ITER 445
Mitigation of the Temperature Margin Reduction due to the Nuclear Radiation on the ITER TF Coils 440
DTT device: Conceptual design of the superconducting magnet system 434
CFD analysis of the ITER first wall 06 panel. Part II: Thermal-hydraulics 432
Validation of the 4C code against data from the HELIOS loop at CEA Grenoble 425
Incorporating Artificial Neural Networks in the dynamic thermal-hydraulic model of a controlled cryogenic circuit 422
Artificial Neural Networks: a viable tool to design heat load smoothing strategies for the ITER Toroidal Field coils 421
Thermal-hydraulic modeling of a novel HTS CICC for nuclear fusion applications 420
Analysis of the DC performance of the ITER CSI coil using the 4C code 418
Overview of the hydraulic characteristics of the ITER Central Solenoid Model Coil conductors after 15 years of test campaigns 415
Modeling of pulsed heat load in a cryogenic SHe loop using Artificial Neural Networks 412
Computational thermal-hydraulic modeling for nuclear fusion and fission applications 412
Prediction, experimental results and analysis of the ITER TF insert coil quench propagation tests, using the 4C code 408
PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS 408
Mechanical analysis of the ENEA TF coil proposal for the EU DEMO fusion reactor 403
Thermal-hydraulic analysis of transients in the HELIOS loop including a CICC section representative of the JT-60SA Central Solenoid 400
Analysis of the cooldown of the ITER central solenoid model coil and insert coil 396
Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data 394
Performance analysis of a graded winding pack design for the EU DEMO TF coil in normal and off-normal conditions 391
Analysis of the Effects of the Nuclear Heat Load on the ITER TF Magnets Temperature Margin 387
Computation of JT-60SA TF coil temperature margin using the 4C code 383
Analysis of AC Losses in the ITER Central Solenoid Insert Coil 383
DTT vacuum vessel, in-vessel coils, and out vessel systems: overview of design and procurement. 380
Numerical analysis of propagation of thermal disturbances in brass-stabilized REBCO tapes 379
Analysis of a protected Loss Of Flow Accident (LOFA) in the ITER TF coil cooling circuit 377
Verification of the Predictive Capabilities of the 4C Code Cryogenic Circuit Model 372
Analyses of low- and high-margin Quench Propagation in the European DEMO TF Coil Winding Pack 370
Validation of the 4C Thermal-Hydraulic Code against 25 kA Safety Discharge in the ITERToroidal Field Model Coil (TFMC) 368
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors 358
Overview of Progress on the EU DEMO Reactor Magnet System Design 346
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 345
CFD analysis of the ITER first wall 06 panel. Part I: Model set-up andflow distribution 345
Dynamic modeling of a Supercritical Helium closed loop with the 4C code 340
Modeling of W7-X superconducting coil cool-down using the 4C code 338
4C modeling of pulsed-load smoothing in the HELIOS facility using a controlled bypass valve 334
Analysis of Quench Propagation in the ITER Poloidal Field Conductor Insert (PFCI) 333
Cutting-edge R&D activities of CIRTEN in support of the Technology Park annexed to the Italian National Repository of radioactive waste 332
4C modeling of the supercritical helium loop HELIOS in isobaric configuration 329
ITER Central Solenoid Insert Test Results 325
Analysis of Quench Propagation in the ITER Central Solenoid Insert (CSI) Coil 315
Modelling the PbLi flow including tritium transport and permeation with GETTHEM 315
Analysis of AC losses in the EAST superconducting magnets using the 4C code 310
Full-core coupled neutronic/thermal-hydraulic modelling of GEN-IV LMFBRs 310
Application of the 4C code to the thermal-hydraulic analysis of the CS superconducting magnets in EAST 305
Design and Integration of the WCLL Tritium Extraction and Removal System into the European DEMO Tokamak Reactor 304
Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code 303
Performance analysis of the NbTi PF coils for the EU DEMO fusion reactor 295
Self Consistent Electrical and Thermal-Hydraulic Model of Faults in Superconducting Magnets: EU DEMO TF Short Circuit During a Fast Discharge 292
Analysis of a Loss-of-Flow Accident (LOFA) in a tokamak superconducting toroidal field coil 292
Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO 291
Innovative concepts in the DTT neutral beam injector 286
Parametric analysis of the ITER TF fast discharge using the 4C code 284
Improved Conceptual Design of the Beamline for the DTT Neutral Beam Injector 280
DTT: A Challenging Framework for a Sound Superconducting Magnets Design 280
Thermal-Hydraulic Simulation of 80 kA Safety Discharge in the ITER Toroidal Field Model Coil (TFMC) using the 4C Code 279
Computational Thermal-Fluid Dynamics analyses of borated water distribution in the Vacuum Vessel of the Divertor Tokamak Test facility 276
Analysis of the thermal-hydraulic effects of a plasma disruption on the DTT TF magnets 276
Thermal-Hydraulic Code-to-Code Benchmark in a Simplified EBR-II Geometry 275
Metamodeling and on-line clustering for loss-of-flow accident precursors identification in a superconducting magnet cryogenic cooling circuit 274
Engineering design of a Permeator Against Vacuum mock-up with niobium membrane 273
Development of an integrated thermo-mechanical simulation environment for quench analyses in HTS cables for fusion 271
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS 268
Advanced methods for loss-of-flow accident precursors identification in a superconducting magnet cryogenic cooling circuit 268
Design of the cryogenic loop for the superconducting toroidal-field magnets of the Divertor Tokamak Test 264
The DEMO magnet system – Status and future challenges 260
First Validation of the FRENETIC Code Thermal-Hydraulic Model against the ENEA Integral Circulation Experiment 252
Characterization of the ITER CS conductor and projection to the ITER CS performance 252
Innovative Concepts in the Design of DTT Neutral Beam Injector. 245
Testing of the ITER CS Module #4 243
Validation of the 4C Code on the AC Loss Tests of a Full-Scale ITER Coil 239
Engineering design of the thermal shield for the Divertor Tokamak Test (DTT) facility 233
Modeling Quench Propagation in the ENEA HTS Cable-In-Conduit Conductor 231
Analysis of the ITER central solenoid insert (CSI) coil stability tests 222
Identification of LOFA precursors in ITER superconducting magnet cryogenic cooling circuit 222
Thermal-hydraulic and mechanical analysis of the Beam Line Components for the DTT Neutral Beam Injector 220
Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption 220
Integrated design strategy for EU-DEMO first wall protection from plasma transients 216
Coupling and Hysteresis Loss Measurements on the ITER CS Module #4 214
Application of the Polynomial Chaos Expansion to the Uncertainty Propagation in Fault Transients in Nuclear Fusion Reactors: DTT TF Fast Current Discharge 213
Progresses in the development of the tritium extraction and removal system for the water-cooled lithium-lead breeding blanket in EUROfusion 212
DTT toroidal field conductor samples test in Sultan: DC and AC characterization 208
Integrated deterministic and probabilistic safety assessment of a superconducting magnet cryogenic cooling circuit for nuclear fusion applications 198
Quench experiments on sub-size HTS Cable-In-Conduit Conductors for fusion applications: Data analysis and model validation 196
Advance in the conceptual design of the European DEMO magnet system 188
Technical summary of the injector for the CTT NBI system 184
Totale 34.896
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Categoria #
all - tutte 97.369
article - articoli 77.737
book - libri 1.228
conference - conferenze 16.797
curatela - curatele 0
other - altro 692
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 193.823
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/20221.414 0 0 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
2025/202611.176 737 662 985 807 755 653 1.420 767 2.163 963 338 926
2026/20271.020 389 458 173 0 0 0 0 0 0 0 0 0
Totale 38.899