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

CAMMI, ANTONIO
 Distribuzione geografica
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Continente #
NA - Nord America 13.214
EU - Europa 6.842
AS - Asia 2.627
AF - Africa 224
SA - Sud America 85
OC - Oceania 45
Continente sconosciuto - Info sul continente non disponibili 15
AN - Antartide 1
Totale 23.053
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Nazione #
US - Stati Uniti d'America 12.821
IT - Italia 2.969
AT - Austria 600
CN - Cina 594
SG - Singapore 431
GB - Regno Unito 426
UA - Ucraina 418
DE - Germania 408
VN - Vietnam 404
FR - Francia 371
FI - Finlandia 369
CA - Canada 366
SE - Svezia 288
IE - Irlanda 240
KR - Corea 234
JO - Giordania 221
NL - Olanda 190
HK - Hong Kong 159
ES - Italia 114
TR - Turchia 101
JP - Giappone 97
BE - Belgio 94
IN - India 85
CH - Svizzera 66
IR - Iran 66
EG - Egitto 64
RU - Federazione Russa 59
DK - Danimarca 46
ID - Indonesia 46
AU - Australia 44
BR - Brasile 44
ZA - Sudafrica 41
TW - Taiwan 37
CZ - Repubblica Ceca 36
RO - Romania 33
BJ - Benin 31
MX - Messico 26
CI - Costa d'Avorio 23
MY - Malesia 23
PK - Pakistan 22
SI - Slovenia 21
DZ - Algeria 20
PL - Polonia 20
CO - Colombia 19
PH - Filippine 19
GR - Grecia 18
IL - Israele 15
EU - Europa 14
MU - Mauritius 11
BD - Bangladesh 10
MA - Marocco 10
NO - Norvegia 9
LB - Libano 8
TN - Tunisia 8
CL - Cile 7
LT - Lituania 7
TH - Thailandia 7
AR - Argentina 6
BO - Bolivia 6
HR - Croazia 6
MO - Macao, regione amministrativa speciale della Cina 6
PS - Palestinian Territory 6
SA - Arabia Saudita 6
HU - Ungheria 5
LI - Liechtenstein 5
LK - Sri Lanka 5
NG - Nigeria 5
RS - Serbia 5
TZ - Tanzania 5
AL - Albania 4
CD - Congo 4
IQ - Iraq 4
KZ - Kazakistan 4
LV - Lettonia 4
UZ - Uzbekistan 4
AE - Emirati Arabi Uniti 3
EE - Estonia 3
KG - Kirghizistan 3
AM - Armenia 2
BG - Bulgaria 2
EC - Ecuador 2
PT - Portogallo 2
SY - Repubblica araba siriana 2
A1 - Anonimo 1
AQ - Antartide 1
BY - Bielorussia 1
CY - Cipro 1
GH - Ghana 1
IM - Isola di Man 1
LA - Repubblica Popolare Democratica del Laos 1
LU - Lussemburgo 1
MK - Macedonia 1
NZ - Nuova Zelanda 1
OM - Oman 1
PE - Perù 1
SV - El Salvador 1
UG - Uganda 1
Totale 23.053
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Città #
Fairfield 1.513
Chandler 1.376
Woodbridge 1.178
Ashburn 972
Houston 932
Milan 923
Wilmington 750
Ann Arbor 681
Seattle 675
Vienna 593
Cambridge 515
Lawrence 260
Singapore 256
Jacksonville 251
Medford 236
Dublin 234
Ottawa 230
Dearborn 226
Amman 219
Dong Ket 188
Beijing 164
Redwood City 162
Helsinki 129
London 95
Rome 95
San Diego 88
Shanghai 88
Delft 82
Málaga 77
Des Moines 76
Brussels 66
Central 59
Los Angeles 56
Redmond 55
Turin 55
New York 54
Chicago 50
Paris 49
Gif-sur-yvette 48
Boardman 42
Princeton 41
Lappeenranta 40
Bresso 39
Montreal 39
Norwalk 39
Dallas 38
Washington 34
Hong Kong 33
Mountain View 32
Tokyo 32
Alexandria 31
Brescia 31
Cotonou 31
Seoul 31
Fremont 30
Grenoble 29
Miami 28
Hefei 26
Johannesburg 25
Suwon 25
Vedano al Lambro 25
Zurich 25
Amsterdam 24
Ankara 24
Sydney 24
Taipei 24
Abidjan 23
Raleigh 23
Istanbul 22
Como 21
Oshawa 21
Zhengzhou 21
Manchester 20
Pohang 20
Torino 20
Auburn Hills 19
Bologna 19
San Jose 19
Prague 18
Falls Church 17
Madrid 17
Padova 17
Columbus 16
Groningen 16
Palermo 16
Phoenix 16
Yongin-si 16
Bergamo 15
Daejeon 15
Ljubljana 15
Seregno 15
Urbana 15
Verona 15
Berkeley 14
Naples 14
Philadelphia 14
College Station 13
Essex 13
Frankfurt am Main 13
Geelong 13
Totale 15.179
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Nome #
Neutrino physics with JUNO 337
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects 332
Multi-Physics Approach to the Modeling and Analysis of Molten Salt Reactors 260
Description of initial reference design and identification of safety aspects 228
Optimization of the pre-conceptual design of the MSFR 202
Development of a control-oriented power plant simulator for the molten salt fast reactor 194
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project 165
CFD study of an air-water flow inside helically coiled pipes 158
A Reduced Order Model for Multi-Group Time-Dependent Parametrized Reactor Spatial Kinetics 155
DYNASTY: An Experimental Loop for the Study of Natural Circulation with Internally Heated Fluids 154
An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor 148
A "Generation III+" Nuclear Reactor for Space Needs 146
Development of a control-oriented simulator for a LFR demonstrator 146
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor 143
A new approach for nuclear reactor analysis based on complex network theory 143
Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor 142
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts 139
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 133
Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation 131
Dynamic performance assessment of MOX and metallic fuel core options for a Gen-IV LFR demonstrator 131
Safety Analysis - Transient Calculations 129
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants 129
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 129
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response 128
An approach to the MSR dynamics and stability analysis 128
Recommendations for an MSFR demonstrator pre-conceptual design 126
A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis 126
Investigation of the MSFR core physics and fuel cycle characteristics 125
Monte Carlo integrated approach to radiological characterization for nuclear facilities decommissioning 125
An Object-Oriented Approach to Simulation of IRIS Dynamic Response 124
Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor 124
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources 123
A scheme of correlation for frictional pressure drop in steam-water two-phase flow in helicoidal tubes 121
Dynamic stability of natural circulation loops for single phase fluids with internal heat generation 120
A Model Predictive Control Approach for the Italian LBE-XADS 119
RELAP5/MOD3.3 study on density wave instabilities in single channel and two parallel channels 119
A zero dimensional model for simulation of TRIGA Mark II dynamic response 119
Transfer Function Modeling of Zero-Power Dynamics of Circulating Fuel Reactors 117
A Preliminary Approach to the Dynamic Behaviour of Circulating Fuel Reactors for Generation IV 116
Development of the ALFRED reactor full power mode control system 114
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR 114
Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches 114
A Generalized Approach to Heat Transfer in Pipe Flow with Internal Heat Generation 113
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics 112
MCNP model of L-54 M nuclear research reactor: development and preliminary verification 112
A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel 110
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 109
An Approach for the Modelling and the Analysis of the MSR Thermo-Hydrodynamic Behaviour 109
Collapse Behavior of Moderately Thick Tubes Pressurized from Outside 108
Dimensional Effects in the Modelling of MSR Dynamics: Moving on from Simplified Schemes of Analysis to a Multi-Physics Modelling Approach 108
Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure 107
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 107
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor 107
Experimental Characterization of Two-Phase Flow Instability Thresholds in Helically Coiled Parallel Channels 107
Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis 107
Modelling of Heat Transfer Phenomena for Vertical and Horizontal Configurations of In-Pool Condensers and Comparison with Experimental Findings 106
Development of best estimate numerical tools for LFR design and safety analysis 106
Gas transfer model to design a ventilator for neonatal total liquid ventilation 105
A coupled neutronics shock physics solver: implementation of an SN neutron transport module 105
Dynamic Mode Decomposition for the Control of Nuclear Power Plants 104
Complete Thermal-Hydraulic Modelling of the Pavia TRIGA Mark II Research Reactor for the Study of the Natural Circulation Regime 104
Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models 103
Object-Oriented Modeling and simulation of a TRIGA reactor plant with Dymola 103
On density wave instability phenomena: modelling and experimental investigation 102
Dynamics in natural circulation loop for internally heated molten salt 102
Analysis of different containment models for IRIS small break LOCA, using GOTHIC and RELAP5 codes 101
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 101
Modelling and analysis of the MSFR transient behaviour 101
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches 100
A CFD-based simulation tool for the stability analysis of natural circulation systems 100
A Multi-Physics Modelling Approach to the Dynamics of Molten Salt Reactors 98
A preliminary approach to the ALFRED reactor control strategy 98
An Arbitrary Lagrangian Eulerian solver for shock imploding fissile materials 98
Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor 98
Thermal hydraulics of liquid-fueled MSRs 97
Local Fusion of an Ensemble of Models for the Reconstruction of Faulty Signals 97
An ensemble approach to sensor fault detection and signal reconstruction for nuclear system control 96
Evaluation of the Coolant Reactivity Coefficient Influence on the Dynamic Response of a Small LFR System 96
A preliminary study of the MSFR dynamics 96
Extension of the FAST code system for the modelling and simulation of MSR dynamics 95
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop 95
A non-equilibrium control oriented model for the pressurizer dynamics 95
The Multi-Physics Modelling Approach Oriented to Safety Analysis of Innovative Nuclear Reactors 94
Analytical models for a small LFR core dynamics studies 94
Assessment of Different Turbulence Models in Helically Coiled Pipes through Comparison with Experimental Data 94
JUNO Physics Prospects 93
Final characterization of the first critical configuration for the TRIGA Mark II reactor of the University of Pavia using the Monte Carlo code MCNP 93
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor 93
Adaptive simulation for failure identification in the Advanced Lead Fast Reactor European Demonstrator 93
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor 93
Study of a new Automatic Reactor Power Control for the TRIGA Mark II Reactor at University of Pavia 92
A Zero Dimensional Model for Simulation of Triga Mark II Dynamic Response 91
Simulazione Dinamica di un Tetto Verde: Modello Matematico ed Esempio Applicativo 90
Analytical and numerical investigation of the heat exchange effect on the dynamic behaviour of natural circulation with internally heated fluids 90
A Simplified Model for a Preliminary Study of the Dynamic Behaviour of a Small GEN IV LFR DEMO 90
Transfer Function Modelling of the Lead-cooled Fast Reactor (LFR) Dynamics 89
Experimental and numerical study of the laminar flow in helically coiled pipes 89
Molten Salt Mixture Properties in RELAP5 Code for Thermodynamic Solar Applications 88
Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics 87
The influence of the wall thermal inertia over a single-phase natural convection loop with internally heated fluids 87
Totale 12.034
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Categoria #
all - tutte 80.187
article - articoli 46.017
book - libri 627
conference - conferenze 27.686
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 1.778
Totale 156.295
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20203.808 0 0 97 311 526 531 578 385 480 273 395 232
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
2023/20243.375 204 390 282 273 253 307 340 290 125 263 328 320
2024/2025761 245 293 223 0 0 0 0 0 0 0 0 0
Totale 23.652