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

LUZZI, LELIO
 Distribuzione geografica
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Continente #
NA - Nord America 11.141
EU - Europa 5.506
AS - Asia 2.082
AF - Africa 125
SA - Sud America 85
OC - Oceania 27
Continente sconosciuto - Info sul continente non disponibili 9
Totale 18.975
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Nazione #
US - Stati Uniti d'America 10.889
IT - Italia 1.867
AT - Austria 524
CN - Cina 481
SG - Singapore 456
UA - Ucraina 449
DE - Germania 429
FR - Francia 364
GB - Regno Unito 358
FI - Finlandia 326
VN - Vietnam 308
SE - Svezia 258
CA - Canada 218
IE - Irlanda 174
NL - Olanda 166
ES - Italia 160
JO - Giordania 152
KR - Corea 146
ID - Indonesia 110
BE - Belgio 109
JP - Giappone 85
CH - Svizzera 70
HK - Hong Kong 63
BR - Brasile 61
TR - Turchia 56
IR - Iran 55
RU - Federazione Russa 55
DK - Danimarca 47
IN - India 42
EG - Egitto 38
MX - Messico 27
RO - Romania 26
TW - Taiwan 24
ZA - Sudafrica 21
GR - Grecia 19
PK - Pakistan 19
AU - Australia 18
BJ - Benin 18
CZ - Repubblica Ceca 16
IL - Israele 15
PL - Polonia 15
NO - Norvegia 14
CI - Costa d'Avorio 13
HU - Ungheria 13
AM - Armenia 12
CL - Cile 12
MY - Malesia 12
PH - Filippine 11
HR - Croazia 10
EU - Europa 9
MA - Marocco 9
NZ - Nuova Zelanda 9
BD - Bangladesh 8
MU - Mauritius 7
NG - Nigeria 7
SA - Arabia Saudita 7
AE - Emirati Arabi Uniti 5
CO - Colombia 5
DZ - Algeria 5
PT - Portogallo 5
AL - Albania 4
BG - Bulgaria 4
RS - Serbia 4
TH - Thailandia 4
AR - Argentina 3
CR - Costa Rica 3
EE - Estonia 3
GL - Groenlandia 3
LI - Liechtenstein 3
LU - Lussemburgo 3
OM - Oman 3
PE - Perù 3
SI - Slovenia 3
AZ - Azerbaigian 2
LT - Lituania 2
SK - Slovacchia (Repubblica Slovacca) 2
SY - Repubblica araba siriana 2
TN - Tunisia 2
UZ - Uzbekistan 2
ZW - Zimbabwe 2
BO - Bolivia 1
BY - Bielorussia 1
CY - Cipro 1
ET - Etiopia 1
GH - Ghana 1
IM - Isola di Man 1
KZ - Kazakistan 1
LV - Lettonia 1
MT - Malta 1
SV - El Salvador 1
UG - Uganda 1
Totale 18.975
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Città #
Chandler 1.169
Fairfield 1.169
Woodbridge 900
Ashburn 711
Wilmington 666
Houston 654
Milan 586
Ann Arbor 548
Seattle 536
Vienna 515
Santa Clara 414
Cambridge 399
Singapore 302
Boardman 283
Dearborn 248
Jacksonville 245
Lawrence 197
Medford 173
Ottawa 171
Dublin 168
Dong Ket 156
Helsinki 154
Amman 152
Beijing 132
Málaga 122
Redwood City 111
Jakarta 89
Brussels 88
London 72
Delft 71
San Diego 66
Rome 60
Des Moines 59
Gif-sur-yvette 57
Shanghai 56
Redmond 54
New York 49
Los Angeles 48
Princeton 46
Hefei 44
Norwalk 43
Washington 39
Auburn Hills 36
Mountain View 33
Paris 33
Frankfurt am Main 29
Falkenstein 28
Tortona 28
Chicago 27
Grafing 27
Turin 27
Tokyo 26
San Jose 25
Amsterdam 24
Columbus 23
Falls Church 22
Munich 21
Taipei 21
Como 20
Johannesburg 20
Pohang 20
Seoul 20
Ankara 19
Madrid 19
Aix-en-Provence 18
Copenhagen 18
Cotonou 18
Phoenix 18
Edinburgh 17
Idaho Falls 17
Central District 16
Guangzhou 16
Bresso 15
Stockholm 15
Nanjing 14
Warsaw 14
Abidjan 13
Bologna 13
College Station 13
Genoa 13
Istanbul 13
Lappeenranta 13
Seregno 13
Zurich 13
Hong Kong 12
La Tour-de-Peilz 12
Miami 12
São Paulo 12
Alexandria 11
Monza 11
Yongin-si 11
Islamabad 10
Los Alamos 10
Montreal 10
Portland 10
Rho 10
Berlin 9
Budapest 9
Camden 9
Dallas 9
Totale 12.837
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Nome #
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects 335
Multi-Physics Approach to the Modeling and Analysis of Molten Salt Reactors 281
Description of initial reference design and identification of safety aspects 244
Report on the improved models of melting temperature and thermal conductivity for MOX fuels and JOG 231
The DarkSide experiment 218
Optimization of the pre-conceptual design of the MSFR 207
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes 178
Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling 166
DarkSide-20k: A 20 tonne two-phase LAr TPC for direct dark matter detection at LNGS 166
DYNASTY: An Experimental Loop for the Study of Natural Circulation with Internally Heated Fluids 161
A Reduced Order Model for Multi-Group Time-Dependent Parametrized Reactor Spatial Kinetics 159
Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation 155
An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor 152
Hybrib Spectrum Molten Salt Reactor 150
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor 149
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 139
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 138
Safety Analysis - Transient Calculations 135
Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis 134
A laser heating study of the CeO2 solid/liquid transition: challenges related to a refractory compound with a very high oxygen pressure 132
DarkSide-50 results and the future liquid argon dark matter program 132
An approach to the MSR dynamics and stability analysis 131
Recommendations for an MSFR demonstrator pre-conceptual design 130
A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis 130
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources 130
Investigation of the MSFR core physics and fuel cycle characteristics 129
Development of best estimate numerical tools for LFR design and safety analysis 125
A Model Predictive Control Approach for the Italian LBE-XADS 123
A Preliminary Approach to the Dynamic Behaviour of Circulating Fuel Reactors for Generation IV 123
DarkSide-20k Preliminary Design Report: The Global Argon Dark Matter Collaboration 123
Dynamic stability of natural circulation loops for single phase fluids with internal heat generation 123
Transfer Function Modeling of Zero-Power Dynamics of Circulating Fuel Reactors 121
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR 120
Development of the ALFRED reactor full power mode control system 119
A Generalized Approach to Heat Transfer in Pipe Flow with Internal Heat Generation 118
An experimental study of grain growth in mixed oxide samples with various microstructures and plutonium concentrations 118
Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches 118
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics 117
A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel 115
Fuel Modelling in Accident Conditions (FUMAC) 115
An Approach for the Modelling and the Analysis of the MSR Thermo-Hydrodynamic Behaviour 115
The molten salt reactor (MSR) in generation IV: Overview and perspectives 115
Modelling of Transient Fission Gas Behaviour in Oxide Fuel and Application to the BISON Code 114
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor 114
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 113
Dimensional Effects in the Modelling of MSR Dynamics: Moving on from Simplified Schemes of Analysis to a Multi-Physics Modelling Approach 112
Collapse Behavior of Moderately Thick Tubes Pressurized from Outside 111
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 111
Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis 111
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS 111
A Thermoelastic Method for Measuring the Thermal Diffusivity of Solids 110
A thermoelastic method for the measurement of thermal expansion coefficient of solids 110
High-temperature and melting behaviour of nanocrystalline refractory compounds: an experimental approach applied to thorium dioxide 110
Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models 109
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches 108
Dynamics in natural circulation loop for internally heated molten salt 108
PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release 107
Modelling and analysis of the MSFR transient behaviour 107
Extension of the TRANSURANUS Code to the Fuel Rod Performance Analysis of LBE-Cooled Nuclear Reactors 105
A Multi-Physics Modelling Approach to the Dynamics of Molten Salt Reactors 105
Development of a Single-Channel Multi-Physics Model for Lead Fast Reactors 105
A CFD-based simulation tool for the stability analysis of natural circulation systems 105
A preliminary approach to the ALFRED reactor control strategy 104
Thermal hydraulics of liquid-fueled MSRs 103
A preliminary study of the MSFR dynamics 103
A multiproperty method and apparatus for thermophysical measurements on solids 101
A semi-empirical model for the formation and depletion of the high burnup structure in UO2 101
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop 101
Incorporation and verification of models and properties in fuel performance codes 100
Extension of the FAST code system for the modelling and simulation of MSR dynamics 99
Multiscale Modelling for the Fission Gas Behaviour in the TRANSURANUS Code 99
Assessment of the Prediction Capability of the TRANSURANUS Fuel Performance Code on the Basis of Power Ramp Tested LWR Fuel Rods 98
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools 98
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant 98
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations 98
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor 97
The Multi-Physics Modelling Approach Oriented to Safety Analysis of Innovative Nuclear Reactors 96
Analytical and numerical investigation of the heat exchange effect on the dynamic behaviour of natural circulation with internally heated fluids 96
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 96
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor 96
Spark plasma sintering of fine uranium carbide powder 96
Finite element limit analysis of anisotropic structures 95
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor 94
Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics 93
The influence of the wall thermal inertia over a single-phase natural convection loop with internally heated fluids 93
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events 93
Cryogenic Characterization of FBK RGB-HD SiPMs 93
Collapse of Thick Tubes Pressurized from Outside: an Accurate Predictive Formula 92
The solidification behaviour of the UO2-ThO2 system in a laser heating study 92
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions 92
Design report of the DYNASTY test facility with passive DHR system 91
Collapse of Thick Tubes Subjected to External Pressure 90
Modelling of Circulating Nuclear Fuels with COMSOL Multiphysics 88
Innovative preparation route for uranium carbide using citric acid as a carbon source 85
Report describing the irradiation experiments selected for the assessment of fuel performance codes 85
Results of the applicative benchmark between TRANSURANUS and GERMINAL on the ASTRID case study 85
Inert matrix and thoria fuels for plutonium elimination 83
Petri-net based modelling approach for ALFRED reactor operation and control system design 83
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis 83
Analysis of Coupled Dynamics of Molten Salt Reactors 82
Totale 12.078
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Categoria #
all - tutte 62.487
article - articoli 35.815
book - libri 1.012
conference - conferenze 13.521
curatela - curatele 0
other - altro 0
patent - brevetti 183
selected - selezionate 0
volume - volumi 2.183
Totale 115.201
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20202.568 0 0 0 0 383 379 488 263 364 222 294 175
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
2023/20242.034 132 273 174 156 171 211 163 168 62 125 129 270
2024/20251.676 119 183 175 200 999 0 0 0 0 0 0 0
Totale 19.396