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

LUZZI, LELIO
 Distribuzione geografica
Salva come PNG Salva come JPEG
Continente #
NA - Nord America 10.261
EU - Europa 5.045
AS - Asia 1.382
AF - Africa 100
SA - Sud America 57
OC - Oceania 23
Continente sconosciuto - Info sul continente non disponibili 9
Totale 16.877
Salva come PNG Salva come JPEG
Nazione #
US - Stati Uniti d'America 10.032
IT - Italia 1.666
AT - Austria 523
UA - Ucraina 448
CN - Cina 379
DE - Germania 368
GB - Regno Unito 334
FR - Francia 318
FI - Finlandia 312
VN - Vietnam 308
SE - Svezia 254
CA - Canada 209
IE - Irlanda 171
JO - Giordania 152
ES - Italia 151
NL - Olanda 144
KR - Corea 118
BE - Belgio 107
JP - Giappone 77
IR - Iran 55
TR - Turchia 52
HK - Hong Kong 50
CH - Svizzera 47
DK - Danimarca 45
BR - Brasile 38
IN - India 38
RU - Federazione Russa 38
SG - Singapore 37
EG - Egitto 36
ID - Indonesia 25
TW - Taiwan 23
RO - Romania 22
ZA - Sudafrica 21
GR - Grecia 19
CZ - Repubblica Ceca 16
AU - Australia 15
PK - Pakistan 14
CI - Costa d'Avorio 13
MX - Messico 13
HU - Ungheria 12
AM - Armenia 11
CL - Cile 11
IL - Israele 11
MY - Malesia 11
EU - Europa 9
PL - Polonia 9
NZ - Nuova Zelanda 8
HR - Croazia 7
MA - Marocco 7
MU - Mauritius 7
CO - Colombia 5
NG - Nigeria 5
PH - Filippine 5
DZ - Algeria 4
PT - Portogallo 4
RS - Serbia 4
BG - Bulgaria 3
CR - Costa Rica 3
EE - Estonia 3
GL - Groenlandia 3
LI - Liechtenstein 3
LU - Lussemburgo 3
NO - Norvegia 3
OM - Oman 3
SA - Arabia Saudita 3
SI - Slovenia 3
TH - Thailandia 3
AE - Emirati Arabi Uniti 2
AL - Albania 2
AR - Argentina 2
BD - Bangladesh 2
SK - Slovacchia (Repubblica Slovacca) 2
SY - Repubblica araba siriana 2
TN - Tunisia 2
ZW - Zimbabwe 2
BO - Bolivia 1
BY - Bielorussia 1
CY - Cipro 1
ET - Etiopia 1
GH - Ghana 1
IM - Isola di Man 1
LT - Lituania 1
MT - Malta 1
SV - El Salvador 1
UG - Uganda 1
Totale 16.877
Salva come PNG Salva come JPEG
Città #
Chandler 1.169
Fairfield 1.169
Woodbridge 900
Wilmington 666
Houston 654
Ashburn 636
Ann Arbor 545
Seattle 536
Milan 530
Vienna 515
Cambridge 399
Dearborn 248
Jacksonville 245
Lawrence 197
Medford 173
Ottawa 170
Dublin 168
Dong Ket 156
Amman 152
Helsinki 152
Beijing 125
Málaga 122
Redwood City 111
Brussels 87
Delft 71
San Diego 66
London 65
Des Moines 59
Gif-sur-yvette 57
Rome 57
Redmond 54
New York 46
Princeton 46
Hefei 44
Norwalk 43
Shanghai 43
Washington 39
Los Angeles 38
Boardman 37
Auburn Hills 36
Mountain View 33
Paris 28
Tortona 28
Grafing 27
Tokyo 24
Columbus 23
Falls Church 22
Johannesburg 20
Pohang 20
Taipei 20
Ankara 19
Chicago 19
Amsterdam 18
Copenhagen 18
Phoenix 18
Edinburgh 17
Idaho Falls 17
Central District 16
Turin 16
Bresso 15
Como 15
Abidjan 13
Bologna 13
College Station 13
Guangzhou 13
Munich 13
Madrid 12
Nanjing 12
San Jose 12
Seoul 12
Aix-en-Provence 11
Alexandria 11
Genoa 11
Stockholm 11
Yongin-si 11
Zurich 11
Frankfurt am Main 10
Miami 10
Monza 10
Portland 10
Rho 10
Berlin 9
Camden 9
Dallas 9
Hangyang 9
Indiana 9
Islamabad 9
Istanbul 9
Los Alamos 9
Mondragon 9
Raleigh 9
Bardolino 8
Berkeley 8
Budapest 8
Grenoble 8
Harbin 8
Hong Kong 8
La Crescenta 8
Lemont 8
Lyngby 8
Totale 11.450
Salva come PNG Salva come JPEG
Nome #
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects 329
Description of initial reference design and identification of safety aspects 217
Multi-Physics Approach to the Modeling and Analysis of Molten Salt Reactors 216
The DarkSide experiment 205
Optimization of the pre-conceptual design of the MSFR 178
Report on the improved models of melting temperature and thermal conductivity for MOX fuels and JOG 168
Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling 159
DarkSide-20k: A 20 tonne two-phase LAr TPC for direct dark matter detection at LNGS 156
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes 154
DYNASTY: An Experimental Loop for the Study of Natural Circulation with Internally Heated Fluids 153
A Reduced Order Model for Multi-Group Time-Dependent Parametrized Reactor Spatial Kinetics 151
Hybrib Spectrum Molten Salt Reactor 141
An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor 140
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor 131
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 131
Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis 129
Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation 129
An approach to the MSR dynamics and stability analysis 127
Safety Analysis - Transient Calculations 126
DarkSide-50 results and the future liquid argon dark matter program 125
Investigation of the MSFR core physics and fuel cycle characteristics 124
Recommendations for an MSFR demonstrator pre-conceptual design 122
A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis 120
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources 120
Dynamic stability of natural circulation loops for single phase fluids with internal heat generation 119
A Model Predictive Control Approach for the Italian LBE-XADS 116
A Preliminary Approach to the Dynamic Behaviour of Circulating Fuel Reactors for Generation IV 115
An experimental study of grain growth in mixed oxide samples with various microstructures and plutonium concentrations 115
Transfer Function Modeling of Zero-Power Dynamics of Circulating Fuel Reactors 114
Development of the ALFRED reactor full power mode control system 113
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 112
Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches 112
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 109
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR 109
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics 109
A Generalized Approach to Heat Transfer in Pipe Flow with Internal Heat Generation 108
A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel 107
Collapse Behavior of Moderately Thick Tubes Pressurized from Outside 107
An Approach for the Modelling and the Analysis of the MSR Thermo-Hydrodynamic Behaviour 107
Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis 106
High-temperature and melting behaviour of nanocrystalline refractory compounds: an experimental approach applied to thorium dioxide 106
A thermoelastic method for the measurement of thermal expansion coefficient of solids 105
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 105
Dimensional Effects in the Modelling of MSR Dynamics: Moving on from Simplified Schemes of Analysis to a Multi-Physics Modelling Approach 105
A Thermoelastic Method for Measuring the Thermal Diffusivity of Solids 104
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor 104
Modelling of Transient Fission Gas Behaviour in Oxide Fuel and Application to the BISON Code 103
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS 103
DarkSide-20k Preliminary Design Report: The Global Argon Dark Matter Collaboration 103
Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models 101
Extension of the TRANSURANUS Code to the Fuel Rod Performance Analysis of LBE-Cooled Nuclear Reactors 100
PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release 100
Modelling and analysis of the MSFR transient behaviour 99
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches 98
A CFD-based simulation tool for the stability analysis of natural circulation systems 98
Fuel Modelling in Accident Conditions (FUMAC) 97
A semi-empirical model for the formation and depletion of the high burnup structure in UO2 96
Multiscale Modelling for the Fission Gas Behaviour in the TRANSURANUS Code 95
A multiproperty method and apparatus for thermophysical measurements on solids 94
Thermal hydraulics of liquid-fueled MSRs 94
The molten salt reactor (MSR) in generation IV: Overview and perspectives 94
A Multi-Physics Modelling Approach to the Dynamics of Molten Salt Reactors 93
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant 93
Extension of the FAST code system for the modelling and simulation of MSR dynamics 92
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor 92
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop 92
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor 92
Spark plasma sintering of fine uranium carbide powder 92
A preliminary study of the MSFR dynamics 91
Assessment of the Prediction Capability of the TRANSURANUS Fuel Performance Code on the Basis of Power Ramp Tested LWR Fuel Rods 90
Analytical and numerical investigation of the heat exchange effect on the dynamic behaviour of natural circulation with internally heated fluids 90
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations 90
A laser heating study of the CeO2 solid/liquid transition: challenges related to a refractory compound with a very high oxygen pressure 89
Finite element limit analysis of anisotropic structures 89
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools 89
Incorporation and verification of models and properties in fuel performance codes 89
A Preliminary Assessment of the T91 Behaviour for the Extension of the TRANSURANUS Code to the Fuel Rod Performance Analysis of LBE Cooled Nuclear Reactors 88
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions 88
The solidification behaviour of the UO2-ThO2 system in a laser heating study 87
Cryogenic Characterization of FBK RGB-HD SiPMs 87
The influence of the wall thermal inertia over a single-phase natural convection loop with internally heated fluids 86
A preliminary approach to the ALFRED reactor control strategy 86
Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics 85
Development of best estimate numerical tools for LFR design and safety analysis 85
Collapse of Thick Tubes Pressurized from Outside: an Accurate Predictive Formula 84
The Multi-Physics Modelling Approach Oriented to Safety Analysis of Innovative Nuclear Reactors 83
Modelling of Circulating Nuclear Fuels with COMSOL Multiphysics 83
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor 82
Development of a Single-Channel Multi-Physics Model for Lead Fast Reactors 81
Innovative preparation route for uranium carbide using citric acid as a carbon source 80
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events 79
Dynamics in natural circulation loop for internally heated molten salt 79
Inert matrix and thoria fuels for plutonium elimination 78
Petri-net based modelling approach for ALFRED reactor operation and control system design 78
Design report of the DYNASTY test facility with passive DHR system 78
Analysis of Coupled Dynamics of Molten Salt Reactors 77
Extension and Validation of the TRANSURANUS Burn-up Model for Helium Production in High Burn-up LWR Fuels 77
Thoria and Inert Matrix Fuels for a Sustainable Nuclear Power 77
The Role of Italian universities/CIRTEN for the engineering study of a fission-fusion hybrid reactor (FFHR) 76
The melting behaviour of oxide nuclear fuels: effects of the oxygen potential studied by laser heating 75
Totale 10.955
Salva come PNG Salva come JPEG
Categoria #
all - tutte 48.744
article - articoli 28.919
book - libri 732
conference - conferenze 10.439
curatela - curatele 0
other - altro 0
patent - brevetti 145
selected - selezionate 0
volume - volumi 1.694
Totale 90.673
Salva come PNG Salva come JPEG


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2018/20191.278 0 0 0 0 0 0 0 0 0 358 515 405
2019/20203.358 224 238 70 258 383 379 488 263 364 222 294 175
2020/20212.335 188 101 192 77 174 122 144 218 170 348 200 401
2021/20222.076 62 255 140 109 212 120 121 133 137 131 272 384
2022/20233.591 319 282 127 368 385 425 79 259 627 212 304 204
2023/20241.605 132 273 174 156 171 211 163 168 62 95 0 0
Totale 17.291