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

LUZZI, LELIO
 Distribuzione geografica
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Continente #
NA - Nord America 18.861
EU - Europa 12.551
AS - Asia 9.026
SA - Sud America 1.615
AF - Africa 555
OC - Oceania 57
Continente sconosciuto - Info sul continente non disponibili 12
Totale 42.677
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Nazione #
US - Stati Uniti d'America 18.351
RU - Federazione Russa 4.198
IT - Italia 2.802
SG - Singapore 2.709
CN - Cina 2.311
BR - Brasile 1.341
VN - Vietnam 1.062
FR - Francia 970
KR - Corea 742
DE - Germania 674
GB - Regno Unito 670
AT - Austria 612
JP - Giappone 534
UA - Ucraina 472
FI - Finlandia 411
NL - Olanda 366
CA - Canada 347
SE - Svezia 302
HK - Hong Kong 286
MA - Marocco 261
IN - India 213
ES - Italia 211
IE - Irlanda 196
JO - Giordania 169
ID - Indonesia 165
BE - Belgio 140
TR - Turchia 128
BD - Bangladesh 103
CH - Svizzera 100
MX - Messico 96
PL - Polonia 94
AR - Argentina 88
TW - Taiwan 82
IR - Iran 78
IQ - Iraq 76
ZA - Sudafrica 67
PK - Pakistan 65
EG - Egitto 55
DK - Danimarca 53
AU - Australia 44
EC - Ecuador 38
VE - Venezuela 38
MY - Malesia 36
RO - Romania 35
SA - Arabia Saudita 34
CL - Cile 33
CZ - Repubblica Ceca 33
GR - Grecia 33
PH - Filippine 33
CI - Costa d'Avorio 31
CO - Colombia 30
UZ - Uzbekistan 30
ET - Etiopia 29
HU - Ungheria 26
LT - Lituania 26
TH - Thailandia 24
IL - Israele 22
PY - Paraguay 22
NO - Norvegia 20
TN - Tunisia 20
AE - Emirati Arabi Uniti 19
BJ - Benin 18
DZ - Algeria 16
KE - Kenya 16
AL - Albania 15
AM - Armenia 13
AZ - Azerbaigian 13
BG - Bulgaria 13
HR - Croazia 12
OM - Oman 12
DO - Repubblica Dominicana 11
NP - Nepal 11
SK - Slovacchia (Repubblica Slovacca) 11
HN - Honduras 10
NG - Nigeria 10
NZ - Nuova Zelanda 10
CR - Costa Rica 9
EU - Europa 9
PS - Palestinian Territory 9
PT - Portogallo 9
KG - Kirghizistan 8
PE - Perù 8
RS - Serbia 8
SI - Slovenia 8
TT - Trinidad e Tobago 8
UY - Uruguay 8
BO - Bolivia 7
LV - Lettonia 7
MU - Mauritius 7
JM - Giamaica 6
KZ - Kazakistan 6
LB - Libano 5
LK - Sri Lanka 5
BY - Bielorussia 4
PA - Panama 4
SN - Senegal 4
SV - El Salvador 4
SY - Repubblica araba siriana 4
AO - Angola 3
CY - Cipro 3
Totale 42.600
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Città #
Ashburn 2.799
San Jose 1.496
Singapore 1.491
Chandler 1.166
Fairfield 1.150
Milan 1.082
Santa Clara 1.036
Woodbridge 894
Moscow 674
Wilmington 662
Houston 659
Vienna 586
Council Bluffs 564
Seattle 556
Ann Arbor 544
Seoul 536
The Dalles 426
Hefei 391
Cambridge 389
Tokyo 387
Beijing 329
Boardman 293
Los Angeles 259
Lauterbourg 258
Dallas 253
Dearborn 248
Jacksonville 248
Ho Chi Minh City 240
Helsinki 206
Lawrence 196
Dublin 189
Hong Kong 184
Medford 173
Ottawa 173
Hanoi 171
Amman 166
London 161
North Charleston 158
Dong Ket 156
Frankfurt am Main 132
São Paulo 130
New York 129
Málaga 122
Kenitra 116
Shanghai 116
Casablanca 115
Redwood City 111
Buffalo 104
Brussels 103
Jakarta 103
Orem 94
Rome 92
Delft 84
Paris 81
Amsterdam 79
Warsaw 71
Chicago 70
Kent 69
San Diego 67
Turin 65
Las Vegas 63
Taipei 62
Des Moines 61
Guangzhou 60
Columbus 58
Gif-sur-yvette 57
Da Nang 54
Montreal 54
Redmond 54
Stockholm 51
Washington 51
Johannesburg 49
Phoenix 48
Ankara 45
Princeton 45
Nuremberg 44
Norwalk 43
Rio de Janeiro 43
Mumbai 38
Düsseldorf 36
Idaho Falls 36
Manchester 36
Auburn Hills 35
Munich 35
Atlanta 34
Boston 34
Mountain View 33
Falkenstein 32
Chennai 31
Denver 31
Haiphong 31
Bologna 30
San Francisco 30
Brooklyn 29
Suwon 29
Tashkent 29
Tortona 29
Abidjan 28
Aix-en-Provence 28
Grafing 27
Totale 25.245
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Nome #
Multi-Physics Approach to the Modeling and Analysis of Molten Salt Reactors 474
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects 408
Report on the improved models of melting temperature and thermal conductivity for MOX fuels and JOG 392
The DarkSide experiment 356
Description of initial reference design and identification of safety aspects 350
The molten salt reactor (MSR) in generation IV: Overview and perspectives 347
DarkSide-20k: A 20 tonne two-phase LAr TPC for direct dark matter detection at LNGS 329
Optimization of the pre-conceptual design of the MSFR 318
Development of best estimate numerical tools for LFR design and safety analysis 313
A laser heating study of the CeO2 solid/liquid transition: challenges related to a refractory compound with a very high oxygen pressure 305
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes 295
The TRANSURANUS fuel performance code 290
Dynamics in natural circulation loop for internally heated molten salt 271
An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor 267
A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis 261
DYNASTY: An Experimental Loop for the Study of Natural Circulation with Internally Heated Fluids 261
Modelling and analysis of the MSFR transient behaviour 254
Safety Analysis - Transient Calculations 253
DarkSide-50 results and the future liquid argon dark matter program 253
Cryogenic Characterization of FBK RGB-HD SiPMs 252
Towards multi-physics description of fuel behaviour for accidental conditions 251
Hybrib Spectrum Molten Salt Reactor 248
A Reduced Order Model for Multi-Group Time-Dependent Parametrized Reactor Spatial Kinetics 247
Fuel Modelling in Accident Conditions (FUMAC) 246
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR 243
Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling 241
Investigation of the MSFR core physics and fuel cycle characteristics 240
Recommendations for an MSFR demonstrator pre-conceptual design 239
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor 238
Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches 238
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources 235
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 234
Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation 233
Design report of the DYNASTY test facility with passive DHR system 231
A Model Predictive Control Approach for the Italian LBE-XADS 227
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 226
DarkSide-20k Preliminary Design Report: The Global Argon Dark Matter Collaboration 226
Fuel performance simulations of ESNII prototypes: Results on the MYRRHA case study 220
A Generalized Approach to Heat Transfer in Pipe Flow with Internal Heat Generation 218
Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models 218
A CFD-based simulation tool for the stability analysis of natural circulation systems 217
Modelling of Transient Fission Gas Behaviour in Oxide Fuel and Application to the BISON Code 215
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 215
Description of new meso-scale models and their implementation in fuel performance codes 214
A Preliminary Approach to the Dynamic Behaviour of Circulating Fuel Reactors for Generation IV 212
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics 212
Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis 211
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop 210
Incorporation and verification of models and properties in fuel performance codes 209
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools 208
An Approach for the Modelling and the Analysis of the MSR Thermo-Hydrodynamic Behaviour 207
A Multi-Physics Modelling Approach to the Dynamics of Molten Salt Reactors 205
Development of a Single-Channel Multi-Physics Model for Lead Fast Reactors 205
A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel 204
A thermoelastic method for the measurement of thermal expansion coefficient of solids 204
Evaluation of Irradiation Damage of Structural Materials for the MSFR 204
Thermal hydraulics of liquid-fueled MSRs 204
A preliminary approach to the ALFRED reactor control strategy 203
A preliminary study of the MSFR dynamics 203
Collapse of Thick Tubes Subjected to External Pressure 199
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor 199
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches 198
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS 198
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 197
An approach to the MSR dynamics and stability analysis 197
Transient simulation of the in-pile performance of a MA-bearing fuel pin 196
A Thermoelastic Method for Measuring the Thermal Diffusivity of Solids 196
A multiproperty method and apparatus for thermophysical measurements on solids 196
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations 196
Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis 193
Collapse Behavior of Moderately Thick Tubes Pressurized from Outside 192
Dimensional Effects in the Modelling of MSR Dynamics: Moving on from Simplified Schemes of Analysis to a Multi-Physics Modelling Approach 192
Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics 191
Assessment of the Prediction Capability of the TRANSURANUS Fuel Performance Code on the Basis of Power Ramp Tested LWR Fuel Rods 190
Collapse of Thick Tubes Pressurized from Outside: an Accurate Predictive Formula 189
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant 189
Description of new correlations and databases for fuel performance codes to be applied to Am bearing fuels 188
Transfer Function Modeling of Zero-Power Dynamics of Circulating Fuel Reactors 188
A semi-empirical model for the formation and depletion of the high burnup structure in UO2 187
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 186
Development of the ALFRED reactor full power mode control system 186
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events 186
A Numerical Assessment of the Load Bearing Capacity of Thick Tubes Pressurized from Outside 183
Review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour 183
Dynamic stability of natural circulation loops for single phase fluids with internal heat generation 183
Extension of the TRANSURANUS Code to the Fuel Rod Performance Analysis of LBE-Cooled Nuclear Reactors 180
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor 180
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 180
Extension of the FAST code system for the modelling and simulation of MSR dynamics 178
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis 178
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor 177
The influence of the wall thermal inertia over a single-phase natural convection loop with internally heated fluids 177
Finite element limit analysis of anisotropic structures 176
A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes 176
Multiscale Modelling for the Fission Gas Behaviour in the TRANSURANUS Code 175
A Multi-Physics Numerical Model for the MSR Core Dynamics 174
An experimental study of grain growth in mixed oxide samples with various microstructures and plutonium concentrations 174
Synthesis of the inert gas behaviour models developed in INSPYRE 173
Fuel pin behaviour under irradiation with high Pu content: Benchmark exercise 172
A Preliminary Approach to the Neutronics of the Molten Salt Reactor by means of COMSOL Multiphysics 172
Totale 22.530
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Categoria #
all - tutte 115.039
article - articoli 62.771
book - libri 1.785
conference - conferenze 25.036
curatela - curatele 0
other - altro 0
patent - brevetti 363
selected - selezionate 0
volume - volumi 4.301
Totale 209.295
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021946 0 0 0 0 0 0 0 0 0 346 200 400
2021/20222.072 62 255 140 109 212 119 121 133 136 130 272 383
2022/20233.583 318 282 127 366 384 423 79 259 626 212 303 204
2023/20242.030 131 271 174 156 171 211 163 168 62 125 129 269
2024/20256.673 119 183 175 200 1.223 737 466 543 809 414 935 869
2025/202618.854 3.290 3.187 880 1.537 1.178 1.113 2.873 1.192 1.580 2.024 0 0
Totale 43.154