CAMMI, ANTONIO
 Distribuzione geografica
Continente #
NA - Nord America 20.286
EU - Europa 15.670
AS - Asia 9.744
SA - Sud America 2.469
AF - Africa 593
OC - Oceania 79
Continente sconosciuto - Info sul continente non disponibili 17
AN - Antartide 1
Totale 48.859
Nazione #
US - Stati Uniti d'America 19.660
RU - Federazione Russa 6.256
IT - Italia 3.743
SG - Singapore 3.465
CN - Cina 2.721
BR - Brasile 2.095
VN - Vietnam 829
DE - Germania 764
GB - Regno Unito 718
FR - Francia 690
AT - Austria 667
KR - Corea 584
NL - Olanda 534
CA - Canada 444
UA - Ucraina 444
FI - Finlandia 426
SE - Svezia 341
HK - Hong Kong 323
IE - Irlanda 258
IN - India 245
JO - Giordania 229
JP - Giappone 211
ID - Indonesia 202
TR - Turchia 175
MA - Marocco 165
ES - Italia 164
BE - Belgio 130
AR - Argentina 118
BD - Bangladesh 118
ZA - Sudafrica 116
MX - Messico 111
CH - Svizzera 101
IR - Iran 98
PL - Polonia 85
EG - Egitto 81
IQ - Iraq 74
AU - Australia 73
CI - Costa d'Avorio 65
TW - Taiwan 65
CO - Colombia 61
CZ - Repubblica Ceca 59
EC - Ecuador 59
PK - Pakistan 59
DK - Danimarca 58
PH - Filippine 41
RO - Romania 40
SA - Arabia Saudita 36
BJ - Benin 32
VE - Venezuela 32
DZ - Algeria 31
AE - Emirati Arabi Uniti 30
GR - Grecia 30
IL - Israele 28
MY - Malesia 28
CL - Cile 27
UZ - Uzbekistan 25
SI - Slovenia 24
BO - Bolivia 23
KE - Kenya 23
PY - Paraguay 22
PE - Perù 19
TN - Tunisia 19
LT - Lituania 18
TH - Thailandia 17
AZ - Azerbaigian 16
KZ - Kazakistan 16
LB - Libano 16
LV - Lettonia 16
EU - Europa 14
HU - Ungheria 14
NO - Norvegia 13
DO - Repubblica Dominicana 12
MO - Macao, regione amministrativa speciale della Cina 12
PS - Palestinian Territory 12
UY - Uruguay 12
JM - Giamaica 11
MU - Mauritius 11
NG - Nigeria 11
PT - Portogallo 11
KG - Kirghizistan 10
LI - Liechtenstein 9
TT - Trinidad e Tobago 9
AL - Albania 8
NP - Nepal 8
BG - Bulgaria 7
BH - Bahrain 7
CR - Costa Rica 7
RS - Serbia 7
ET - Etiopia 6
HN - Honduras 6
HR - Croazia 6
LK - Sri Lanka 6
LU - Lussemburgo 6
OM - Oman 6
AM - Armenia 5
BY - Bielorussia 5
GE - Georgia 5
NI - Nicaragua 5
NZ - Nuova Zelanda 5
SK - Slovacchia (Repubblica Slovacca) 5
Totale 48.764
Città #
Ashburn 2.976
Singapore 2.037
Santa Clara 1.656
Fairfield 1.497
Chandler 1.373
Milan 1.217
Woodbridge 1.171
Houston 938
Moscow 898
Wilmington 744
Hefei 739
Seattle 708
Ann Arbor 684
Vienna 630
Cambridge 507
Boardman 420
Council Bluffs 387
Beijing 369
Los Angeles 344
Lawrence 260
Jacksonville 254
Dublin 246
Medford 236
Seoul 234
Ottawa 231
Amman 227
Dearborn 226
London 212
Dallas 199
Dong Ket 188
São Paulo 180
Ho Chi Minh City 166
Redwood City 162
Kent 153
Helsinki 152
Frankfurt am Main 151
Hong Kong 151
Shanghai 142
Buffalo 138
New York 129
Casablanca 124
Jakarta 124
Tokyo 117
Amsterdam 116
Rome 115
Turin 108
Chicago 107
Delft 97
Hanoi 90
San Diego 88
Brussels 86
Nuremberg 86
Málaga 77
Paris 77
Des Moines 76
The Dalles 75
Montreal 72
Johannesburg 70
Stockholm 63
Abidjan 61
Warsaw 61
Central 59
Düsseldorf 56
Redmond 55
Rio de Janeiro 51
San Jose 50
Suwon 50
Lappeenranta 49
Gif-sur-yvette 48
Phoenix 48
Belo Horizonte 47
Ankara 45
Atlanta 41
Princeton 40
Bresso 39
Dhaka 39
Norwalk 39
Tianjin 38
Washington 38
Bogotá 37
Manchester 37
Orem 37
Miami 36
Zhengzhou 36
Zurich 36
Porto Alegre 35
Prague 35
Boston 34
Brasília 34
Curitiba 34
Guangzhou 34
Istanbul 34
Taipei 34
Brescia 32
Brooklyn 32
Cotonou 32
Mountain View 32
Sydney 32
Alexandria 31
Chennai 31
Totale 26.769
Nome #
Neutrino physics with JUNO 540
Multi-Physics Approach to the Modeling and Analysis of Molten Salt Reactors 406
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects 382
Description of initial reference design and identification of safety aspects 307
Development of a control-oriented power plant simulator for the molten salt fast reactor 286
Optimization of the pre-conceptual design of the MSFR 281
Development of best estimate numerical tools for LFR design and safety analysis 268
Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor 263
JUNO Physics Prospects 260
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project 243
DYNASTY: An Experimental Loop for the Study of Natural Circulation with Internally Heated Fluids 231
A "Generation III+" Nuclear Reactor for Space Needs 230
An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor 230
CFD study of an air-water flow inside helically coiled pipes 229
Safety Analysis - Transient Calculations 221
A scheme of correlation for frictional pressure drop in steam-water two-phase flow in helicoidal tubes 219
A Reduced Order Model for Multi-Group Time-Dependent Parametrized Reactor Spatial Kinetics 218
Dynamics in natural circulation loop for internally heated molten salt 212
Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation 209
A new approach for nuclear reactor analysis based on complex network theory 209
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 208
Development of a control-oriented simulator for a LFR demonstrator 205
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor 205
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 205
Recommendations for an MSFR demonstrator pre-conceptual design 203
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources 203
Monte Carlo integrated approach to radiological characterization for nuclear facilities decommissioning 202
An Object-Oriented Approach to Simulation of IRIS Dynamic Response 200
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR 200
OpenMC Model Validation of the TRIGA Mark II Reactor 199
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants 198
A Model Predictive Control Approach for the Italian LBE-XADS 197
Design report of the DYNASTY test facility with passive DHR system 196
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response 196
A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis 195
1D Modelica Modeling of the DYNASTY-eDYNASTY Coupled Natural Circulation Loops 192
Dynamic Mode Decomposition for the Control of Nuclear Power Plants 191
OpenMC Analysis of TRIGA Mark II Reactor Void and Temperature Reactivity Coefficients 189
Experimental Characterization of Two-Phase Flow Instability Thresholds in Helically Coiled Parallel Channels 189
Detection of the Diffuse Supernova Neutrino Background with JUNO 187
Development of an OpenFOAM multiphysics solver for solid fission products transport in the Molten Salt Fast Reactor 187
Numerical methodology for design and evaluation of natural circulation systems for MSR applications 186
MCNP model of L-54 M nuclear research reactor: development and preliminary verification 186
A Generalized Approach to Heat Transfer in Pipe Flow with Internal Heat Generation 185
A Preliminary Approach to the Dynamic Behaviour of Circulating Fuel Reactors for Generation IV 183
RELAP5/MOD3.3 study on density wave instabilities in single channel and two parallel channels 183
Investigation of the MSFR core physics and fuel cycle characteristics 183
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop 182
Modelling and analysis of the MSFR transient behaviour 181
Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor 180
Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches 179
Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor 179
A zero dimensional model for simulation of TRIGA Mark II dynamic response 178
Dynamics of Natural Circulation in Presence of Distributed Heating: Results of the SAMOFAR CFD Simulation Campaign 177
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 177
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics 177
A coupled neutronics shock physics solver: implementation of an SN neutron transport module 177
Dynamic performance assessment of MOX and metallic fuel core options for a Gen-IV LFR demonstrator 175
A preliminary approach to the ALFRED reactor control strategy 174
An Approach for the Modelling and the Analysis of the MSR Thermo-Hydrodynamic Behaviour 174
An approach to the MSR dynamics and stability analysis 174
Development of a Single-Channel Multi-Physics Model for Lead Fast Reactors 173
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor 173
A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel 172
A CFD-based simulation tool for the stability analysis of natural circulation systems 172
Application of the dynamic mode decomposition approach to the dispersion of radioactive contaminants in air 169
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events 168
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches 168
TAO Conceptual Design Report: A Precision Measurement of the Reactor Antineutrino Spectrum with Sub-percent Energy Resolution 167
Thermal hydraulics of liquid-fueled MSRs 166
Potential of Core-Collapse Supernova Neutrino Detection at JUNO 165
A Multi-Physics Modelling Approach to the Dynamics of Molten Salt Reactors 165
Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis 165
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts 165
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 164
Development of the ALFRED reactor full power mode control system 164
Feasibility of detecting B8 solar neutrinos at JUNO 163
On density wave instability phenomena: modelling and experimental investigation 163
Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure 163
A preliminary study of the MSFR dynamics 163
Collapse Behavior of Moderately Thick Tubes Pressurized from Outside 162
ALFRED reactor and hybrid systems: A test case 161
Transfer Function Modeling of Zero-Power Dynamics of Circulating Fuel Reactors 161
A non-equilibrium control oriented model for the pressurizer dynamics 161
Dimensional Effects in the Modelling of MSR Dynamics: Moving on from Simplified Schemes of Analysis to a Multi-Physics Modelling Approach 161
A Reduced Order Kalman Filter for Computational Fluid-Dynamics Applications 160
Modelling of Heat Transfer Phenomena for Vertical and Horizontal Configurations of In-Pool Condensers and Comparison with Experimental Findings 159
Analysis of different containment models for IRIS small break LOCA, using GOTHIC and RELAP5 codes 159
Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models 159
Dynamic stability of natural circulation loops for single phase fluids with internal heat generation 159
A Novel Approach for Parametric Dynamic Mode Decomposition: Application to the DYNASTY Experimental Facility 158
A Dynamic Model of a Lead-Cooled Fast Reactor (LFR) with a Supercritical Water Steam Cycle 158
A Serpent/OpenFOAM coupling approach for the study of the fuel burnup 158
Transfer Function Modelling of the Lead-cooled Fast Reactor (LFR) Dynamics 157
Assessment of Different Turbulence Models in Helically Coiled Pipes through Comparison with Experimental Data 157
Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core 157
FEniCSx-OpenMC Coupling for Neutronic Calculation with Temperature Feedback 156
Experimental and theoretical studies on density wave instabilities in helically coiled tubes 156
A 3D MULTI-PHYSICS MODELLING OF THE TRIGA MARK II REACTOR 156
Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics 154
Totale 19.518
Categoria #
all - tutte 147.884
article - articoli 82.124
book - libri 1.071
conference - conferenze 53.953
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 3.108
Totale 288.140


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/20211.920 0 0 0 0 0 176 271 254 204 316 189 510
2021/20222.477 99 216 146 111 249 138 139 205 200 223 287 464
2022/20234.843 406 425 144 394 436 738 167 384 796 229 419 305
2023/20243.359 203 388 282 273 253 307 340 290 125 263 324 311
2024/202510.542 233 289 288 243 1.864 1.246 568 865 1.475 709 1.385 1.377
2025/202616.203 4.953 4.945 1.589 2.466 1.809 441 0 0 0 0 0 0
Totale 49.531