RE.PUBLIC@POLIMI pubblicazioni di ricerca del Politecnico di Milano

CAMMI, ANTONIO
 Distribuzione geografica
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Continente #
NA - Nord America 15.339
EU - Europa 7.343
AS - Asia 3.321
AF - Africa 232
SA - Sud America 126
OC - Oceania 45
Continente sconosciuto - Info sul continente non disponibili 15
AN - Antartide 1
Totale 26.422
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Nazione #
US - Stati Uniti d'America 14.947
IT - Italia 3.160
SG - Singapore 740
CN - Cina 724
AT - Austria 613
DE - Germania 476
GB - Regno Unito 440
UA - Ucraina 422
FR - Francia 408
VN - Vietnam 404
FI - Finlandia 382
CA - Canada 364
SE - Svezia 289
NL - Olanda 284
KR - Corea 267
IE - Irlanda 248
JO - Giordania 221
HK - Hong Kong 191
ID - Indonesia 145
JP - Giappone 120
ES - Italia 117
TR - Turchia 111
BE - Belgio 100
IN - India 93
RU - Federazione Russa 85
BR - Brasile 74
IR - Iran 73
CH - Svizzera 67
EG - Egitto 64
TW - Taiwan 47
DK - Danimarca 46
AU - Australia 44
ZA - Sudafrica 41
CZ - Repubblica Ceca 40
RO - Romania 33
BJ - Benin 31
PK - Pakistan 27
MX - Messico 26
PH - Filippine 26
DZ - Algeria 24
CI - Costa d'Avorio 23
MY - Malesia 23
SI - Slovenia 23
GR - Grecia 22
PL - Polonia 22
CO - Colombia 19
IL - Israele 18
BD - Bangladesh 16
EU - Europa 14
MA - Marocco 13
CL - Cile 11
MU - Mauritius 11
BO - Bolivia 10
NO - Norvegia 10
SA - Arabia Saudita 10
LB - Libano 8
LT - Lituania 8
TN - Tunisia 8
AR - Argentina 7
TH - Thailandia 7
AE - Emirati Arabi Uniti 6
HR - Croazia 6
HU - Ungheria 6
MO - Macao, regione amministrativa speciale della Cina 6
PS - Palestinian Territory 6
UZ - Uzbekistan 6
IQ - Iraq 5
KZ - Kazakistan 5
LI - Liechtenstein 5
LK - Sri Lanka 5
NG - Nigeria 5
RS - Serbia 5
TZ - Tanzania 5
AL - Albania 4
CD - Congo 4
LU - Lussemburgo 4
LV - Lettonia 4
PT - Portogallo 4
EE - Estonia 3
KG - Kirghizistan 3
AM - Armenia 2
BG - Bulgaria 2
EC - Ecuador 2
OM - Oman 2
PE - Perù 2
SK - Slovacchia (Repubblica Slovacca) 2
SY - Repubblica araba siriana 2
UG - Uganda 2
A1 - Anonimo 1
AQ - Antartide 1
BY - Bielorussia 1
CY - Cipro 1
DO - Repubblica Dominicana 1
GH - Ghana 1
IM - Isola di Man 1
LA - Repubblica Popolare Democratica del Laos 1
MK - Macedonia 1
NZ - Nuova Zelanda 1
SV - El Salvador 1
VE - Venezuela 1
Totale 26.422
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Città #
Santa Clara 1.604
Fairfield 1.513
Chandler 1.376
Woodbridge 1.178
Milan 998
Ashburn 986
Houston 932
Wilmington 750
Seattle 694
Ann Arbor 681
Vienna 600
Singapore 533
Cambridge 515
Boardman 409
Lawrence 261
Jacksonville 251
Dublin 239
Medford 236
Ottawa 230
Dearborn 226
Amman 219
Dong Ket 188
Beijing 177
Redwood City 162
Helsinki 139
Jakarta 107
Rome 107
London 96
Shanghai 92
San Diego 88
Delft 85
Amsterdam 79
Málaga 77
Des Moines 76
Brussels 70
Los Angeles 63
Central 59
Turin 58
New York 56
Paris 55
Redmond 55
Chicago 52
Gif-sur-yvette 48
Hong Kong 47
Tokyo 45
Dallas 43
Lappeenranta 42
Princeton 41
Bresso 39
Montreal 39
Norwalk 39
Seoul 37
Washington 34
Mountain View 32
Alexandria 31
Brescia 31
Cotonou 31
Taipei 31
Frankfurt am Main 30
Fremont 30
Miami 28
Como 27
Grenoble 27
Suwon 27
Hefei 26
Zurich 26
Istanbul 25
Johannesburg 25
Vedano al Lambro 25
Zhengzhou 25
Ankara 24
Falkenstein 24
Sydney 24
Abidjan 23
Raleigh 23
San Jose 23
Manchester 22
Oshawa 21
Pohang 21
Nuremberg 20
Prague 20
Torino 20
Auburn Hills 19
Bologna 19
Monza 19
College Station 17
Daejeon 17
Falls Church 17
Groningen 17
Ljubljana 17
Madrid 17
Moscow 17
Padova 17
Columbus 16
Palermo 16
Phoenix 16
Yongin-si 16
Bergamo 15
Guangzhou 15
Urbana 15
Totale 17.870
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Nome #
Neutrino physics with JUNO 371
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects 336
Multi-Physics Approach to the Modeling and Analysis of Molten Salt Reactors 289
Description of initial reference design and identification of safety aspects 250
Optimization of the pre-conceptual design of the MSFR 217
Development of a control-oriented power plant simulator for the molten salt fast reactor 212
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project 193
DYNASTY: An Experimental Loop for the Study of Natural Circulation with Internally Heated Fluids 175
Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation 172
CFD study of an air-water flow inside helically coiled pipes 167
A Reduced Order Model for Multi-Group Time-Dependent Parametrized Reactor Spatial Kinetics 163
Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor 161
An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor 159
Development of a control-oriented simulator for a LFR demonstrator 156
A new approach for nuclear reactor analysis based on complex network theory 156
JUNO Physics Prospects 155
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor 153
A "Generation III+" Nuclear Reactor for Space Needs 151
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 144
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts 143
Safety Analysis - Transient Calculations 142
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 142
Dynamic performance assessment of MOX and metallic fuel core options for a Gen-IV LFR demonstrator 139
Development of best estimate numerical tools for LFR design and safety analysis 137
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response 136
An approach to the MSR dynamics and stability analysis 135
A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis 134
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants 134
Monte Carlo integrated approach to radiological characterization for nuclear facilities decommissioning 134
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources 134
Investigation of the MSFR core physics and fuel cycle characteristics 133
Recommendations for an MSFR demonstrator pre-conceptual design 132
An Object-Oriented Approach to Simulation of IRIS Dynamic Response 132
Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor 132
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR 130
A scheme of correlation for frictional pressure drop in steam-water two-phase flow in helicoidal tubes 130
RELAP5/MOD3.3 study on density wave instabilities in single channel and two parallel channels 127
A zero dimensional model for simulation of TRIGA Mark II dynamic response 126
A Model Predictive Control Approach for the Italian LBE-XADS 125
A Preliminary Approach to the Dynamic Behaviour of Circulating Fuel Reactors for Generation IV 125
Transfer Function Modeling of Zero-Power Dynamics of Circulating Fuel Reactors 125
Dynamic stability of natural circulation loops for single phase fluids with internal heat generation 124
Development of a Single-Channel Multi-Physics Model for Lead Fast Reactors 123
MCNP model of L-54 M nuclear research reactor: development and preliminary verification 123
A Generalized Approach to Heat Transfer in Pipe Flow with Internal Heat Generation 122
Development of the ALFRED reactor full power mode control system 122
Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches 122
An Approach for the Modelling and the Analysis of the MSR Thermo-Hydrodynamic Behaviour 121
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics 120
Experimental Characterization of Two-Phase Flow Instability Thresholds in Helically Coiled Parallel Channels 119
A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel 118
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor 118
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 117
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 117
A coupled neutronics shock physics solver: implementation of an SN neutron transport module 116
Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor 116
Dimensional Effects in the Modelling of MSR Dynamics: Moving on from Simplified Schemes of Analysis to a Multi-Physics Modelling Approach 116
Modelling of Heat Transfer Phenomena for Vertical and Horizontal Configurations of In-Pool Condensers and Comparison with Experimental Findings 115
Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure 114
Collapse Behavior of Moderately Thick Tubes Pressurized from Outside 113
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches 113
Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis 113
Dynamics in natural circulation loop for internally heated molten salt 113
Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models 112
Gas transfer model to design a ventilator for neonatal total liquid ventilation 112
Object-Oriented Modeling and simulation of a TRIGA reactor plant with Dymola 112
Complete Thermal-Hydraulic Modelling of the Pavia TRIGA Mark II Research Reactor for the Study of the Natural Circulation Regime 112
Modelling and analysis of the MSFR transient behaviour 112
Analysis of different containment models for IRIS small break LOCA, using GOTHIC and RELAP5 codes 111
Dynamic Mode Decomposition for the Control of Nuclear Power Plants 111
On density wave instability phenomena: modelling and experimental investigation 110
Thermal hydraulics of liquid-fueled MSRs 110
A CFD-based simulation tool for the stability analysis of natural circulation systems 110
An Arbitrary Lagrangian Eulerian solver for shock imploding fissile materials 109
Development of an OpenFOAM multiphysics solver for solid fission products transport in the Molten Salt Fast Reactor 108
A Multi-Physics Modelling Approach to the Dynamics of Molten Salt Reactors 108
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop 107
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 107
A preliminary approach to the ALFRED reactor control strategy 107
A preliminary study of the MSFR dynamics 107
A non-equilibrium control oriented model for the pressurizer dynamics 104
Local Fusion of an Ensemble of Models for the Reconstruction of Faulty Signals 103
Extension of the FAST code system for the modelling and simulation of MSR dynamics 102
Analytical models for a small LFR core dynamics studies 102
Design report of the DYNASTY test facility with passive DHR system 102
Assessment of Different Turbulence Models in Helically Coiled Pipes through Comparison with Experimental Data 102
Study of a new Automatic Reactor Power Control for the TRIGA Mark II Reactor at University of Pavia 101
An ensemble approach to sensor fault detection and signal reconstruction for nuclear system control 101
Analytical and numerical investigation of the heat exchange effect on the dynamic behaviour of natural circulation with internally heated fluids 101
Evaluation of the Coolant Reactivity Coefficient Influence on the Dynamic Response of a Small LFR System 100
Final characterization of the first critical configuration for the TRIGA Mark II reactor of the University of Pavia using the Monte Carlo code MCNP 100
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor 100
Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core 100
Simulazione Dinamica di un Tetto Verde: Modello Matematico ed Esempio Applicativo 99
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor 99
A Simplified Model for a Preliminary Study of the Dynamic Behaviour of a Small GEN IV LFR DEMO 99
Transfer Function Modelling of the Lead-cooled Fast Reactor (LFR) Dynamics 98
The Multi-Physics Modelling Approach Oriented to Safety Analysis of Innovative Nuclear Reactors 98
Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics 98
The influence of the wall thermal inertia over a single-phase natural convection loop with internally heated fluids 98
Totale 13.174
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Categoria #
all - tutte 93.154
article - articoli 52.675
book - libri 745
conference - conferenze 32.817
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 2.008
Totale 181.399
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20202.343 0 0 0 0 0 0 578 385 480 273 395 232
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
2024/20254.192 233 289 288 243 1.868 1.248 23 0 0 0 0 0
Totale 27.071