LUZZI, LELIO
 Distribuzione geografica
Continente #
NA - Nord America 7941
EU - Europa 3501
AS - Asia 885
AF - Africa 54
SA - Sud America 37
Continente sconosciuto - Info sul continente non disponibili 9
OC - Oceania 8
Totale 12435
Nazione #
US - Stati Uniti d'America 7741
IT - Italia 1243
AT - Austria 483
UA - Ucraina 440
CN - Cina 317
VN - Vietnam 305
DE - Germania 271
SE - Svezia 240
GB - Regno Unito 196
CA - Canada 191
FR - Francia 182
FI - Finlandia 159
NL - Olanda 118
KR - Corea 64
JP - Giappone 37
BE - Belgio 36
BR - Brasile 32
IR - Iran 31
TR - Turchia 27
IN - India 25
RU - Federazione Russa 23
HK - Hong Kong 22
CH - Svizzera 21
ZA - Sudafrica 20
DK - Danimarca 18
EG - Egitto 16
GR - Grecia 16
TW - Taiwan 15
RO - Romania 14
CZ - Repubblica Ceca 13
ID - Indonesia 12
ES - Italia 11
EU - Europa 9
PK - Pakistan 9
AM - Armenia 8
MU - Mauritius 7
MX - Messico 7
HU - Ungheria 6
AU - Australia 4
DZ - Algeria 4
NZ - Nuova Zelanda 4
PH - Filippine 4
CO - Colombia 3
MY - Malesia 3
SG - Singapore 3
AL - Albania 2
HR - Croazia 2
IE - Irlanda 2
MA - Marocco 2
NO - Norvegia 2
TN - Tunisia 2
AR - Argentina 1
CL - Cile 1
CR - Costa Rica 1
ET - Etiopia 1
GH - Ghana 1
IL - Israele 1
LT - Lituania 1
OM - Oman 1
PL - Polonia 1
RS - Serbia 1
SA - Arabia Saudita 1
SV - El Salvador 1
UG - Uganda 1
Totale 12435
Città #
Fairfield 1169
Woodbridge 900
Wilmington 666
Houston 651
Ann Arbor 545
Seattle 522
Vienna 480
Ashburn 475
Cambridge 399
Milan 377
Chandler 297
Dearborn 248
Jacksonville 245
Lawrence 196
Medford 173
Ottawa 168
Dong Ket 156
Beijing 121
Redwood City 111
Delft 67
San Diego 66
Des Moines 59
Gif-sur-yvette 57
Redmond 54
Princeton 46
Hefei 44
Norwalk 43
Auburn Hills 36
Rome 35
Mountain View 33
Shanghai 32
Grafing 27
Brussels 25
Falls Church 22
London 20
Johannesburg 19
Central District 16
Phoenix 16
Taipei 15
Guangzhou 13
Idaho Falls 12
Nanjing 12
Los Angeles 10
Tokyo 10
Hangyang 9
Indiana 9
Los Alamos 9
Mondragon 9
Ankara 8
Bardolino 8
La Crescenta 8
Lyngby 8
New York 8
Venezia 8
Viareggio 8
Berkeley 7
Brescia 7
Como 7
Dallas 7
Fremont 7
Lausanne 7
Monza 7
Rho 7
Rotterdam 7
Savona 7
Seoul 7
Seregno 7
Torino 7
Zhengzhou 7
Alzano Lombardo 6
Amsterdam 6
Munich 6
Nanterre 6
Oak Ridge 6
Paris 6
Rodigo 6
Segrate 6
Aachen 5
Bandung 5
Changsha 5
Cuneo 5
Kunming 5
La Spezia 5
Leopoldshafen 5
Minneapolis 5
Moscow 5
Napoli 5
Pembroke 5
Raleigh 5
Recco 5
San Francisco 5
Seongnam 5
Tong 5
Udine 5
Villeurbanne 5
Atlanta 4
Bologna 4
Casorate Sempione 4
Cassano D'adda 4
Chabahar 4
Totale 9036
Nome #
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects 268
The DarkSide experiment 176
Multi-Physics Approach to the Modeling and Analysis of Molten Salt Reactors 150
Description of initial reference design and identification of safety aspects 149
Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling 145
Optimization of the pre-conceptual design of the MSFR 129
DarkSide-20k: A 20 tonne two-phase LAr TPC for direct dark matter detection at LNGS 125
A Reduced Order Model for Multi-Group Time-Dependent Parametrized Reactor Spatial Kinetics 122
Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation 118
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 118
An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor 115
Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis 114
An experimental study of grain growth in mixed oxide samples with various microstructures and plutonium concentrations 113
DYNASTY: An Experimental Loop for the Study of Natural Circulation with Internally Heated Fluids 113
Hybrib Spectrum Molten Salt Reactor 112
An approach to the MSR dynamics and stability analysis 111
Investigation of the MSFR core physics and fuel cycle characteristics 107
Dynamic stability of natural circulation loops for single phase fluids with internal heat generation 107
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources 102
Development of the ALFRED reactor full power mode control system 101
High-temperature and melting behaviour of nanocrystalline refractory compounds: an experimental approach applied to thorium dioxide 99
Recommendations for an MSFR demonstrator pre-conceptual design 98
A Model Predictive Control Approach for the Italian LBE-XADS 96
A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis 96
Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches 96
Safety Analysis - Transient Calculations 92
Spark plasma sintering of fine uranium carbide powder 92
A Preliminary Approach to the Dynamic Behaviour of Circulating Fuel Reactors for Generation IV 90
PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release 90
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor 90
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics 90
Dimensional Effects in the Modelling of MSR Dynamics: Moving on from Simplified Schemes of Analysis to a Multi-Physics Modelling Approach 90
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR 89
Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis 89
A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel 88
A thermoelastic method for the measurement of thermal expansion coefficient of solids 88
An Approach for the Modelling and the Analysis of the MSR Thermo-Hydrodynamic Behaviour 88
A Thermoelastic Method for Measuring the Thermal Diffusivity of Solids 87
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions 87
Transfer Function Modeling of Zero-Power Dynamics of Circulating Fuel Reactors 86
Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models 86
Modelling of Transient Fission Gas Behaviour in Oxide Fuel and Application to the BISON Code 85
DarkSide-50 results and the future liquid argon dark matter program 85
Extension of the TRANSURANUS Code to the Fuel Rod Performance Analysis of LBE-Cooled Nuclear Reactors 84
A Generalized Approach to Heat Transfer in Pipe Flow with Internal Heat Generation 84
A semi-empirical model for the formation and depletion of the high burnup structure in UO2 84
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 83
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor 83
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS 83
The solidification behaviour of the UO2-ThO2 system in a laser heating study 82
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches 82
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor 82
Collapse Behavior of Moderately Thick Tubes Pressurized from Outside 80
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop 80
Extension of the FAST code system for the modelling and simulation of MSR dynamics 79
Multiscale Modelling for the Fission Gas Behaviour in the TRANSURANUS Code 79
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 79
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes 79
A preliminary study of the MSFR dynamics 77
A multiproperty method and apparatus for thermophysical measurements on solids 76
DarkSide-20k Preliminary Design Report: The Global Argon Dark Matter Collaboration 76
Modelling and analysis of the MSFR transient behaviour 76
Analytical and numerical investigation of the heat exchange effect on the dynamic behaviour of natural circulation with internally heated fluids 75
A CFD-based simulation tool for the stability analysis of natural circulation systems 75
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor 74
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant 74
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 74
Assessment of the Prediction Capability of the TRANSURANUS Fuel Performance Code on the Basis of Power Ramp Tested LWR Fuel Rods 72
The Multi-Physics Modelling Approach Oriented to Safety Analysis of Innovative Nuclear Reactors 72
Innovative preparation route for uranium carbide using citric acid as a carbon source 72
A preliminary approach to the ALFRED reactor control strategy 72
Thermal hydraulics of liquid-fueled MSRs 71
Extension and Validation of the TRANSURANUS Burn-up Model for Helium Production in High Burn-up LWR Fuels 70
Modelling of Circulating Nuclear Fuels with COMSOL Multiphysics 70
The Role of Italian universities/CIRTEN for the engineering study of a fission-fusion hybrid reactor (FFHR) 69
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools 69
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations 69
A Multi-Physics Modelling Approach to the Dynamics of Molten Salt Reactors 68
Collapse of Thick Tubes Pressurized from Outside: an Accurate Predictive Formula 67
Finite element limit analysis of anisotropic structures 67
Collapse of Thick Cylinders under Radial Pressure and Axial Load 67
Microhardness and Young's modulus of high burn-up UO2 fuel 67
Cryogenic Characterization of FBK RGB-HD SiPMs 67
Inert matrix and thoria fuels for plutonium elimination 66
Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics 66
Fuel Modelling in Accident Conditions (FUMAC) 66
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor 66
The melting behaviour of oxide nuclear fuels: effects of the oxygen potential studied by laser heating 65
Thermal contact resistance calibration for thermal diffusivity measurement of metals by the thermoelastic method 65
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor 63
A reduced order model for investigating the dynamics of the Gen-IV LFR coolant pool 63
The ZrC–C eutectic structure and melting behaviour: A high-temperature radiance spectroscopy 62
The influence of the wall thermal inertia over a single-phase natural convection loop with internally heated fluids 62
Vaporization behaviour of the Molten Salt Fast Reactor fuel: The LiF-ThF4-UF4 system 62
Analysis of Coupled Dynamics of Molten Salt Reactors 61
Development of a Single-Channel Multi-Physics Model for Lead Fast Reactors 61
Petri-net based modelling approach for ALFRED reactor operation and control system design 61
Object-oriented modelling and simulation for the ALFRED dynamics 60
Collapse of Nuclear Reactor SG Tubes Pressurized From Outside: The Influence of Imperfections 60
Modelling and Control Strategy of the Italian LBE-XADS 60
Totale 8750
Categoria #
all - tutte 16015
article - articoli 9360
book - libri 316
conference - conferenze 3940
curatela - curatele 0
other - altro 0
patent - brevetti 56
selected - selezionate 0
volume - volumi 590
Totale 30277


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2017/20181688 00040 5830 426574 11615123657
2018/20191965 21368137 67129 9376 147358515405
2019/20203358 22423870258 383379 488263 364222294175
2020/20212335 18810119277 174122 144218 170348200401
2021/20222076 62255140109 212120 121133 137131272384
2022/2023724 3192821230 00 00 0000
Totale 12819