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

CAMMI, ANTONIO
 Distribuzione geografica
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Continente #
NA - Nord America 16.606
EU - Europa 8.672
AS - Asia 5.362
SA - Sud America 1.477
AF - Africa 303
OC - Oceania 59
Continente sconosciuto - Info sul continente non disponibili 15
AN - Antartide 1
Totale 32.495
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Nazione #
US - Stati Uniti d'America 16.139
IT - Italia 3.482
SG - Singapore 2.061
BR - Brasile 1.327
CN - Cina 878
DE - Germania 703
AT - Austria 651
FR - Francia 625
GB - Regno Unito 526
NL - Olanda 488
KR - Corea 458
UA - Ucraina 430
FI - Finlandia 415
VN - Vietnam 414
CA - Canada 383
SE - Svezia 309
IE - Irlanda 257
HK - Hong Kong 236
JO - Giordania 225
ID - Indonesia 158
JP - Giappone 151
TR - Turchia 144
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
MX - Messico 55
ZA - Sudafrica 55
TW - Taiwan 54
DK - Danimarca 53
BD - Bangladesh 50
PL - Polonia 44
PK - Pakistan 43
IQ - Iraq 38
MA - Marocco 38
CO - Colombia 36
RO - Romania 36
AR - Argentina 34
PH - Filippine 33
BJ - Benin 31
GR - Grecia 29
DZ - Algeria 26
CI - Costa d'Avorio 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
HU - Ungheria 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
LI - Liechtenstein 7
PS - Palestinian Territory 7
HR - Croazia 6
MO - Macao, regione amministrativa speciale della Cina 6
PE - Perù 6
RS - Serbia 6
LK - Sri Lanka 5
TZ - Tanzania 5
AM - Armenia 4
BG - Bulgaria 4
CD - Congo 4
LA - Repubblica Popolare Democratica del Laos 4
LU - Lussemburgo 4
TT - Trinidad e Tobago 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
BA - Bosnia-Erzegovina 2
BH - Bahrain 2
CR - Costa Rica 2
Totale 32.463
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Città #
Santa Clara 1.616
Fairfield 1.497
Chandler 1.373
Singapore 1.172
Woodbridge 1.171
Milan 1.108
Ashburn 1.089
Houston 922
Wilmington 744
Seattle 699
Ann Arbor 678
Vienna 621
Cambridge 507
Boardman 416
Council Bluffs 379
Lawrence 260
Jacksonville 252
Dublin 246
Medford 236
Ottawa 229
Dearborn 226
Beijing 224
Amman 223
Dong Ket 188
Redwood City 162
Seoul 158
Helsinki 150
Los Angeles 136
Rome 113
London 112
Jakarta 110
Shanghai 108
Frankfurt am Main 106
Amsterdam 103
São Paulo 102
Turin 95
Delft 91
San Diego 87
Nuremberg 82
Brussels 78
Hong Kong 77
Málaga 77
Des Moines 76
Chicago 69
New York 69
Paris 67
Tokyo 65
Hefei 60
Central 59
Düsseldorf 56
Redmond 55
Gif-sur-yvette 48
Dallas 47
The Dalles 47
Montreal 46
Lappeenranta 43
San Jose 42
Suwon 42
Princeton 40
Rio de Janeiro 40
Bresso 39
Norwalk 39
Prague 34
Washington 34
Taipei 33
Ankara 32
Brescia 32
Johannesburg 32
Mountain View 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
Sydney 27
Zhengzhou 26
Abidjan 25
Brasília 25
Pohang 25
Vedano al Lambro 25
Warsaw 25
Bogotá 24
Falkenstein 24
Manchester 24
Raleigh 23
Dhaka 22
Porto Alegre 22
Bologna 21
Oshawa 21
Turku 21
Totale 20.120
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Nome #
Neutrino physics with JUNO 454
Multi-Physics Approach to the Modeling and Analysis of Molten Salt Reactors 353
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects 351
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 207
Development of best estimate numerical tools for LFR design and safety analysis 206
Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor 192
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 182
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
Dynamic Mode Decomposition for the Control of Nuclear Power Plants 169
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 169
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
A "Generation III+" Nuclear Reactor for Space Needs 163
Safety Analysis - Transient Calculations 161
Dynamics in natural circulation loop for internally heated molten salt 159
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 157
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 151
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response 150
Monte Carlo integrated approach to radiological characterization for nuclear facilities decommissioning 149
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
An Object-Oriented Approach to Simulation of IRIS Dynamic Response 143
Experimental Characterization of Two-Phase Flow Instability Thresholds in Helically Coiled Parallel Channels 143
A Model Predictive Control Approach for the Italian LBE-XADS 141
RELAP5/MOD3.3 study on density wave instabilities in single channel and two parallel channels 141
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
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 139
A Generalized Approach to Heat Transfer in Pipe Flow with Internal Heat Generation 137
Dynamic stability of natural circulation loops for single phase fluids with internal heat generation 137
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 131
TAO Conceptual Design Report: A Precision Measurement of the Reactor Antineutrino Spectrum with Sub-percent Energy Resolution 130
Development of an OpenFOAM multiphysics solver for solid fission products transport in the Molten Salt Fast Reactor 129
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics 129
Detection of the Diffuse Supernova Neutrino Background with JUNO 128
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 Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 127
A coupled neutronics shock physics solver: implementation of an SN neutron transport module 127
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
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 124
A preliminary approach to the ALFRED reactor control strategy 122
A Multi-Physics Modelling Approach to the Dynamics of Molten Salt Reactors 121
On density wave instability phenomena: modelling and experimental investigation 121
A non-equilibrium control oriented model for the pressurizer dynamics 121
Gas transfer model to design a ventilator for neonatal total liquid ventilation 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
Dynamics of Natural Circulation in Presence of Distributed Heating: Results of the SAMOFAR CFD Simulation Campaign 118
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 118
Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core 118
A preliminary study of the MSFR dynamics 118
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
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor 116
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events 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
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 14.952
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Categoria #
all - tutte 113.361
article - articoli 63.201
book - libri 909
conference - conferenze 40.715
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 2.433
Totale 220.619
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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
2020/20212.805 226 141 176 143 199 176 271 254 204 316 189 510
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
2024/202510.380 233 289 288 243 1.864 1.246 568 865 1.475 709 1.385 1.215
Totale 33.166