CAMMI, ANTONIO
 Distribuzione geografica
Continente #
NA - Nord America 16.593
EU - Europa 8.650
AS - Asia 5.234
SA - Sud America 1.466
AF - Africa 302
OC - Oceania 59
Continente sconosciuto - Info sul continente non disponibili 15
AN - Antartide 1
Totale 32.320
Nazione #
US - Stati Uniti d'America 16.132
IT - Italia 3.468
SG - Singapore 1.997
BR - Brasile 1.317
CN - Cina 842
DE - Germania 703
AT - Austria 650
FR - Francia 624
GB - Regno Unito 525
NL - Olanda 486
KR - Corea 439
UA - Ucraina 430
FI - Finlandia 415
VN - Vietnam 411
CA - Canada 380
SE - Svezia 309
IE - Irlanda 259
HK - Hong Kong 236
JO - Giordania 226
ID - Indonesia 158
JP - Giappone 149
TR - Turchia 142
IN - India 136
ES - Italia 131
RU - Federazione Russa 124
BE - Belgio 110
IR - Iran 86
CH - Svizzera 77
EG - Egitto 73
CZ - Repubblica Ceca 58
AU - Australia 57
ZA - Sudafrica 55
TW - Taiwan 54
DK - Danimarca 53
MX - Messico 53
BD - Bangladesh 49
PL - Polonia 43
PK - Pakistan 41
IQ - Iraq 38
MA - Marocco 38
CO - Colombia 36
RO - Romania 36
AR - Argentina 33
PH - Filippine 33
BJ - Benin 31
GR - Grecia 29
CI - Costa d'Avorio 25
DZ - Algeria 25
EC - Ecuador 24
SI - Slovenia 24
IL - Israele 23
MY - Malesia 23
AE - Emirati Arabi Uniti 22
SA - Arabia Saudita 20
UZ - Uzbekistan 19
CL - Cile 17
BO - Bolivia 15
EU - Europa 14
LT - Lituania 13
KE - Kenya 11
LV - Lettonia 11
MU - Mauritius 11
NO - Norvegia 11
TN - Tunisia 11
AZ - Azerbaigian 10
TH - Thailandia 10
VE - Venezuela 10
DO - Repubblica Dominicana 9
KG - Kirghizistan 9
KZ - Kazakistan 9
PT - Portogallo 9
LB - Libano 8
NG - Nigeria 8
AL - Albania 7
HU - Ungheria 7
LI - Liechtenstein 7
PS - Palestinian Territory 7
HR - Croazia 6
MO - Macao, regione amministrativa speciale della Cina 6
PE - Perù 6
LK - Sri Lanka 5
RS - Serbia 5
TZ - Tanzania 5
AM - Armenia 4
BG - Bulgaria 4
CD - Congo 4
LA - Repubblica Popolare Democratica del Laos 4
LU - Lussemburgo 4
UY - Uruguay 4
CY - Cipro 3
EE - Estonia 3
JM - Giamaica 3
KH - Cambogia 3
OM - Oman 3
PY - Paraguay 3
SK - Slovacchia (Repubblica Slovacca) 3
TT - Trinidad e Tobago 3
BA - Bosnia-Erzegovina 2
BH - Bahrain 2
CR - Costa Rica 2
Totale 32.288
Città #
Santa Clara 1.621
Fairfield 1.516
Chandler 1.376
Woodbridge 1.178
Singapore 1.120
Milan 1.102
Ashburn 1.033
Houston 933
Wilmington 750
Seattle 707
Ann Arbor 682
Vienna 621
Cambridge 518
Boardman 418
Council Bluffs 380
Lawrence 261
Jacksonville 251
Dublin 248
Medford 236
Ottawa 230
Dearborn 226
Amman 224
Beijing 223
Dong Ket 188
Redwood City 162
Seoul 157
Helsinki 149
Los Angeles 135
Rome 113
London 112
Jakarta 110
Shanghai 108
Frankfurt am Main 106
Amsterdam 103
São Paulo 101
Turin 95
Delft 91
San Diego 88
Nuremberg 82
Brussels 78
Hong Kong 77
Málaga 77
Des Moines 76
New York 69
Chicago 68
Paris 67
Tokyo 63
Central 59
Düsseldorf 56
Redmond 55
Gif-sur-yvette 48
Dallas 47
The Dalles 47
Montreal 45
Lappeenranta 43
Suwon 42
Princeton 41
Rio de Janeiro 40
Bresso 39
Norwalk 39
Prague 34
Washington 34
Taipei 33
Ankara 32
Brescia 32
Johannesburg 32
Mountain View 32
San Jose 32
Alexandria 31
Belo Horizonte 31
Cotonou 31
Stockholm 31
College Station 30
Fremont 30
Istanbul 30
Grenoble 29
Miami 29
Lauterbourg 28
Moscow 28
Munich 28
Phoenix 28
Zurich 28
Como 27
Hefei 27
Sydney 27
Zhengzhou 26
Abidjan 25
Brasília 25
Pohang 25
Vedano al Lambro 25
Bogotá 24
Falkenstein 24
Manchester 24
Warsaw 24
Raleigh 23
Porto Alegre 22
Bologna 21
Dhaka 21
Oshawa 21
Turku 21
Totale 20.035
Nome #
Neutrino physics with JUNO 449
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects 351
Multi-Physics Approach to the Modeling and Analysis of Molten Salt Reactors 345
Description of initial reference design and identification of safety aspects 274
Optimization of the pre-conceptual design of the MSFR 244
Development of a control-oriented power plant simulator for the molten salt fast reactor 243
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project 210
JUNO Physics Prospects 206
Development of best estimate numerical tools for LFR design and safety analysis 193
Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor 188
DYNASTY: An Experimental Loop for the Study of Natural Circulation with Internally Heated Fluids 187
CFD study of an air-water flow inside helically coiled pipes 182
An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor 181
Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation 177
A Reduced Order Model for Multi-Group Time-Dependent Parametrized Reactor Spatial Kinetics 175
Development of a control-oriented simulator for a LFR demonstrator 169
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 168
A new approach for nuclear reactor analysis based on complex network theory 168
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor 166
Safety Analysis - Transient Calculations 161
A "Generation III+" Nuclear Reactor for Space Needs 161
Dynamics in natural circulation loop for internally heated molten salt 159
Dynamic Mode Decomposition for the Control of Nuclear Power Plants 157
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 156
Recommendations for an MSFR demonstrator pre-conceptual design 154
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts 153
A scheme of correlation for frictional pressure drop in steam-water two-phase flow in helicoidal tubes 150
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response 148
Monte Carlo integrated approach to radiological characterization for nuclear facilities decommissioning 148
Dynamic performance assessment of MOX and metallic fuel core options for a Gen-IV LFR demonstrator 148
A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis 147
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR 147
Investigation of the MSFR core physics and fuel cycle characteristics 146
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants 146
A Preliminary Approach to the Dynamic Behaviour of Circulating Fuel Reactors for Generation IV 144
A zero dimensional model for simulation of TRIGA Mark II dynamic response 144
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources 144
Experimental Characterization of Two-Phase Flow Instability Thresholds in Helically Coiled Parallel Channels 143
An Object-Oriented Approach to Simulation of IRIS Dynamic Response 142
RELAP5/MOD3.3 study on density wave instabilities in single channel and two parallel channels 140
Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor 140
An approach to the MSR dynamics and stability analysis 140
A Model Predictive Control Approach for the Italian LBE-XADS 139
Design report of the DYNASTY test facility with passive DHR system 139
MCNP model of L-54 M nuclear research reactor: development and preliminary verification 137
Dynamic stability of natural circulation loops for single phase fluids with internal heat generation 137
A Generalized Approach to Heat Transfer in Pipe Flow with Internal Heat Generation 136
Transfer Function Modeling of Zero-Power Dynamics of Circulating Fuel Reactors 135
Development of a Single-Channel Multi-Physics Model for Lead Fast Reactors 135
Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches 135
Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor 135
An Approach for the Modelling and the Analysis of the MSR Thermo-Hydrodynamic Behaviour 135
A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel 134
Development of the ALFRED reactor full power mode control system 133
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop 132
Thermal hydraulics of liquid-fueled MSRs 131
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor 130
TAO Conceptual Design Report: A Precision Measurement of the Reactor Antineutrino Spectrum with Sub-percent Energy Resolution 129
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics 129
Numerical methodology for design and evaluation of natural circulation systems for MSR applications 127
Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure 127
A coupled neutronics shock physics solver: implementation of an SN neutron transport module 127
Detection of the Diffuse Supernova Neutrino Background with JUNO 126
Modelling of Heat Transfer Phenomena for Vertical and Horizontal Configurations of In-Pool Condensers and Comparison with Experimental Findings 126
Collapse Behavior of Moderately Thick Tubes Pressurized from Outside 126
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 126
Development of an OpenFOAM multiphysics solver for solid fission products transport in the Molten Salt Fast Reactor 125
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches 125
Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis 125
Dimensional Effects in the Modelling of MSR Dynamics: Moving on from Simplified Schemes of Analysis to a Multi-Physics Modelling Approach 125
Modelling and analysis of the MSFR transient behaviour 125
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 124
Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models 124
A CFD-based simulation tool for the stability analysis of natural circulation systems 123
On density wave instability phenomena: modelling and experimental investigation 121
A preliminary approach to the ALFRED reactor control strategy 121
A Multi-Physics Modelling Approach to the Dynamics of Molten Salt Reactors 120
Gas transfer model to design a ventilator for neonatal total liquid ventilation 120
A non-equilibrium control oriented model for the pressurizer dynamics 120
Object-Oriented Modeling and simulation of a TRIGA reactor plant with Dymola 119
Complete Thermal-Hydraulic Modelling of the Pavia TRIGA Mark II Research Reactor for the Study of the Natural Circulation Regime 119
An Arbitrary Lagrangian Eulerian solver for shock imploding fissile materials 119
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 118
A preliminary study of the MSFR dynamics 118
Dynamics of Natural Circulation in Presence of Distributed Heating: Results of the SAMOFAR CFD Simulation Campaign 117
Analysis of different containment models for IRIS small break LOCA, using GOTHIC and RELAP5 codes 117
Analytical models for a small LFR core dynamics studies 117
Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core 117
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor 116
Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics 115
Final characterization of the first critical configuration for the TRIGA Mark II reactor of the University of Pavia using the Monte Carlo code MCNP 115
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events 115
Study of a new Automatic Reactor Power Control for the TRIGA Mark II Reactor at University of Pavia 114
Extension of the FAST code system for the modelling and simulation of MSR dynamics 113
Experimental and theoretical studies on density wave instabilities in helically coiled tubes 113
An ensemble approach to sensor fault detection and signal reconstruction for nuclear system control 112
Transfer Function Modelling of the Lead-cooled Fast Reactor (LFR) Dynamics 112
Local Fusion of an Ensemble of Models for the Reconstruction of Faulty Signals 111
Assessment of Different Turbulence Models in Helically Coiled Pipes through Comparison with Experimental Data 111
Instabilities of burnup calculations in a SERPENT/OPENFOAM coupling 111
Totale 14.877
Categoria #
all - tutte 112.408
article - articoli 62.556
book - libri 894
conference - conferenze 40.511
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 2.409
Totale 218.778


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/2020232 0 0 0 0 0 0 0 0 0 0 0 232
2020/20212.840 227 142 205 143 199 176 271 255 204 318 189 511
2021/20222.481 99 216 146 111 249 139 139 205 201 224 287 465
2022/20234.851 407 425 144 396 437 740 167 384 797 229 420 305
2023/20243.363 204 390 282 273 253 307 340 290 125 263 324 312
2024/202510.112 233 289 288 243 1.868 1.248 568 867 1.477 710 1.385 936
Totale 32.991