LUZZI, LELIO
 Distribuzione geografica
Continente #
NA - Nord America 2536
EU - Europa 2473
AS - Asia 1231
AF - Africa 144
SA - Sud America 78
OC - Oceania 21
Continente sconosciuto - Info sul continente non disponibili 4
Totale 6487
Nazione #
US - Stati Uniti d'America 2394
IT - Italia 1109
CN - Cina 472
RU - Federazione Russa 217
FR - Francia 198
TR - Turchia 144
GB - Regno Unito 131
DE - Germania 127
CZ - Repubblica Ceca 106
CA - Canada 104
NL - Olanda 99
KR - Corea 96
JP - Giappone 94
RO - Romania 83
IR - Iran 81
IN - India 80
VN - Vietnam 69
EG - Egitto 61
CH - Svizzera 53
AT - Austria 50
ID - Indonesia 48
ZA - Sudafrica 40
DK - Danimarca 38
BR - Brasile 35
GR - Grecia 34
ES - Italia 32
BE - Belgio 31
UA - Ucraina 31
SE - Svezia 28
MX - Messico 24
TW - Taiwan 24
HK - Hong Kong 20
AR - Argentina 19
CL - Cile 18
AU - Australia 16
DZ - Algeria 16
TH - Thailandia 16
FI - Finlandia 15
PL - Polonia 15
AE - Emirati Arabi Uniti 13
BG - Bulgaria 13
PK - Pakistan 13
SC - Seychelles 10
HU - Ungheria 9
IL - Israele 9
LT - Lituania 9
SK - Slovacchia (Repubblica Slovacca) 9
BD - Bangladesh 8
HN - Honduras 8
HR - Croazia 7
JO - Giordania 7
MA - Marocco 7
PT - Portogallo 7
BZ - Belize 6
SG - Singapore 6
SI - Slovenia 6
MY - Malesia 5
NO - Norvegia 5
UZ - Uzbekistan 5
IE - Irlanda 4
MN - Mongolia 4
NZ - Nuova Zelanda 4
SA - Arabia Saudita 4
BT - Bhutan 3
EU - Europa 3
SY - Repubblica araba siriana 3
BA - Bosnia-Erzegovina 2
BO - Bolivia 2
CO - Colombia 2
LY - Libia 2
MZ - Mozambico 2
PH - Filippine 2
RS - Serbia 2
TN - Tunisia 2
VE - Venezuela 2
A2 - ???statistics.table.value.countryCode.A2??? 1
AM - Armenia 1
EE - Estonia 1
FJ - Figi 1
GH - Ghana 1
IQ - Iraq 1
KE - Kenya 1
LB - Libano 1
LU - Lussemburgo 1
LV - Lettonia 1
NG - Nigeria 1
NP - Nepal 1
PS - Palestinian Territory 1
UG - Uganda 1
Totale 6487
Città #
Milan 269
Fairfield 248
Santa Cruz 170
Buffalo 169
Houston 150
Jinan 150
Seattle 128
Woodbridge 109
Ashburn 95
Cambridge 89
Wilmington 80
Ann Arbor 62
Guangzhou 52
Istanbul 51
Rome 45
Vienna 45
Gif-sur-yvette 42
Dong Ket 39
Moscow 39
Shanghai 38
Phoenix 37
Ottawa 36
Bucharest 31
Henderson 31
Ankara 30
Torino 30
Mountain View 28
Beijing 27
Las Vegas 27
Delft 24
Muizenberg 24
Lausanne 23
Norwalk 23
San Diego 23
Shenyang 23
Clearwater 21
Heerenveen 20
Los Angeles 20
Taipei 19
Tokyo 19
Xian 18
Boardman 17
Dallas 17
Chicago 15
Pembroke 15
Changsha 14
Harbin 14
Seoul 14
Abbiategrasso 13
Idaho Falls 13
Central District 12
London 12
Paris 12
Pushkino 12
Raleigh 12
Saint Louis 12
Sarapul 12
Athens 11
Bengaluru 11
Brierley Hill 11
Council Bluffs 11
Gavirate 11
Saint Petersburg 11
Toronto 11
Duncan 10
Jakarta 10
Perugia 10
Riva 10
Feasterville Trevose 9
Frederiksberg 9
Gurgaon 9
Nardò 9
Pitesti 9
Provo 9
San Jose 9
Turin 9
University Park 9
Wuhan 9
Atlanta 8
Cairo 8
Costa Mesa 8
Hefei 8
Lake Forest 8
Milpitas 8
Petten 8
Tanta 8
Yellow Springs 8
Buenos Aires 7
Chabahar 7
Dubai 7
Genoa 7
Hamilton 7
Lemont 7
Marseille 7
Monroeville 7
New York 7
Prague 7
San Francisco 7
Absecon 6
Belize City 6
Totale 3188
Nome #
Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches, file e0c31c0d-c0f8-4599-e053-1705fe0aef77 745
Fuel Modelling in Accident Conditions (FUMAC), file e0c31c0e-fee8-4599-e053-1705fe0aef77 571
Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis, file e0c31c0d-2fb9-4599-e053-1705fe0aef77 310
The molten salt reactor (MSR) in generation IV: Overview and perspectives, file e0c31c0d-6a55-4599-e053-1705fe0aef77 299
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor, file e0c31c0d-8364-4599-e053-1705fe0aef77 297
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects, file e0c31c0c-e3e6-4599-e053-1705fe0aef77 256
Modelling and analysis of the MSFR transient behaviour, file e0c31c0d-d7dc-4599-e053-1705fe0aef77 233
Object-oriented modelling and simulation for the ALFRED dynamics, file e0c31c0d-6393-4599-e053-1705fe0aef77 189
A preliminary approach to the ALFRED reactor control strategy, file e0c31c0d-66e1-4599-e053-1705fe0aef77 176
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor, file e0c31c0d-1f54-4599-e053-1705fe0aef77 166
Vaporization behaviour of a PuF3-containing fuel mixture for the Molten Salt Fast Reactor, file e0c31c0f-346e-4599-e053-1705fe0aef77 158
DarkSide-20k Preliminary Design Report: The Global Argon Dark Matter Collaboration, file e0c31c11-287f-4599-e053-1705fe0aef77 152
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics, file e0c31c0e-779f-4599-e053-1705fe0aef77 140
Vaporization behaviour of the Molten Salt Fast Reactor fuel: The LiF-ThF4-UF4 system, file e0c31c0b-f8b3-4599-e053-1705fe0aef77 139
Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling, file e0c31c0e-7d2c-4599-e053-1705fe0aef77 138
Dynamic stability of natural circulation loops for single phase fluids with internal heat generation, file e0c31c0e-6273-4599-e053-1705fe0aef77 137
Innovative preparation route for uranium carbide using citric acid as a carbon source, file e0c31c09-cecb-4599-e053-1705fe0aef77 127
The Role of Italian universities/CIRTEN for the engineering study of a fission-fusion hybrid reactor (FFHR), file e0c31c0a-7b8f-4599-e053-1705fe0aef77 125
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches, file e0c31c0d-7420-4599-e053-1705fe0aef77 124
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor, file e0c31c0c-7580-4599-e053-1705fe0aef77 119
The solidification behaviour of the UO2-ThO2 system in a laser heating study, file e0c31c08-1e6f-4599-e053-1705fe0aef77 118
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools, file e0c31c0c-1c20-4599-e053-1705fe0aef77 113
Synthesis of plutonium trifluoride by hydro-fluorination and novel thermodynamic data for the PuF3-LiF system, file e0c31c0b-c09f-4599-e053-1705fe0aef77 110
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes, file e0c31c0f-4faa-4599-e053-1705fe0aef77 110
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations, file e0c31c0b-9f7d-4599-e053-1705fe0aef77 103
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS, file e0c31c0f-3db2-4599-e053-1705fe0aef77 98
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant, file e0c31c0c-8282-4599-e053-1705fe0aef77 97
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources, file e0c31c0a-38b1-4599-e053-1705fe0aef77 94
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor, file e0c31c08-1ec8-4599-e053-1705fe0aef77 87
Microhardness and Young's modulus of high burn-up UO2 fuel, file e0c31c09-bec0-4599-e053-1705fe0aef77 85
Spark plasma sintering of fine uranium carbide powder, file e0c31c09-fb14-4599-e053-1705fe0aef77 84
DarkSide-20k: A 20 tonne two-phase LAr TPC for direct dark matter detection at LNGS, file e0c31c0f-ff4d-4599-e053-1705fe0aef77 76
High-temperature and melting behaviour of nanocrystalline refractory compounds: an experimental approach applied to thorium dioxide, file e0c31c07-bdd7-4599-e053-1705fe0aef77 65
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation, file e0c31c0f-aa25-4599-e053-1705fe0aef77 58
Design and construction of a new detector to measure ultra-low radioactive-isotope contamination of argon, file e0c31c0f-6f93-4599-e053-1705fe0aef77 57
Development of best estimate numerical tools for LFR design and safety analysis, file e0c31c11-2334-4599-e053-1705fe0aef77 57
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients, file e0c31c10-072f-4599-e053-1705fe0aef77 47
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes, file e0c31c10-d8a9-4599-e053-1705fe0aef77 47
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions, file e0c31c12-7f7d-4599-e053-1705fe0aef77 43
Development of the ALFRED reactor full power mode control system, file e0c31c0e-77a0-4599-e053-1705fe0aef77 42
Isobaric heat capacity of solid and liquid thorium tetrafluoride, file e0c31c0f-2e56-4599-e053-1705fe0aef77 39
On the melting behaviour of calcium monoxide under different atmospheres: A laser heating study, file e0c31c0d-ead1-4599-e053-1705fe0aef77 37
Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics, file e0c31c0d-d7dd-4599-e053-1705fe0aef77 36
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications, file e0c31c0f-a502-4599-e053-1705fe0aef77 35
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor, file e0c31c0e-77a7-4599-e053-1705fe0aef77 33
Review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour, file e0c31c10-f6f8-4599-e053-1705fe0aef77 32
A preliminary approach to the MSFR control issues, file e0c31c0d-a8d6-4599-e053-1705fe0aef77 30
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors, file e0c31c11-730b-4599-e053-1705fe0aef77 29
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment, file e0c31c11-66e1-4599-e053-1705fe0aef77 28
Report on the improved models of melting temperature and thermal conductivity for MOX fuels and JOG, file e0c31c11-0a0c-4599-e053-1705fe0aef77 21
Incorporation and verification of models and properties in fuel performance codes, file e0c31c11-3282-4599-e053-1705fe0aef77 20
Results of the applicative benchmark between TRANSURANUS and GERMINAL on the ASTRID case study, file e0c31c11-5faa-4599-e053-1705fe0aef77 17
Synthesis of the inert gas behaviour models developed in INSPYRE, file e0c31c11-000c-4599-e053-1705fe0aef77 15
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations, file e0c31c11-269a-4599-e053-1705fe0aef77 15
A laser heating study of the CeO2 solid/liquid transition: challenges related to a refractory compound with a very high oxygen pressure, file e0c31c0e-99d1-4599-e053-1705fe0aef77 13
On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation, file e0c31c12-e999-4599-e053-1705fe0aef77 13
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor, file e0c31c0e-83ce-4599-e053-1705fe0aef77 11
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution, file e0c31c12-87ff-4599-e053-1705fe0aef77 11
Cryogenic Characterization of FBK RGB-HD SiPMs, file e0c31c0b-88d1-4599-e053-1705fe0aef77 10
Laser melting of nano-crystalline uranium dioxide, file e0c31c0d-6892-4599-e053-1705fe0aef77 10
SiPM-matrix readout of two-phase argon detectors using electroluminescence in the visible and near infrared range, file e0c31c11-2bf9-4599-e053-1705fe0aef77 10
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor, file e0c31c11-f94e-4599-e053-1705fe0aef77 10
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations, file e0c31c09-c080-4599-e053-1705fe0aef77 9
DarkSide-20k: A 20 tonne two-phase LAr TPC for direct dark matter detection at LNGS, file e0c31c0b-c015-4599-e053-1705fe0aef77 9
Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data, file e0c31c11-831e-4599-e053-1705fe0aef77 9
Synthesis of the First User Group Meeting, file e0c31c11-000a-4599-e053-1705fe0aef77 8
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor, file e0c31c0c-de49-4599-e053-1705fe0aef77 7
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events, file e0c31c0c-fcc9-4599-e053-1705fe0aef77 7
Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions, file e0c31c0f-0a02-4599-e053-1705fe0aef77 7
Report describing the irradiation experiments selected for the assessment of fuel performance codes, file e0c31c11-43a5-4599-e053-1705fe0aef77 7
Reduced Order Methods for the Improvement of Control-Oriented Modelling of Nuclear Power Plants, file e0c31c0b-29e5-4599-e053-1705fe0aef77 6
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR, file e0c31c0b-9728-4599-e053-1705fe0aef77 6
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System, file e0c31c0d-432c-4599-e053-1705fe0aef77 6
A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes, file e0c31c12-890d-4599-e053-1705fe0aef77 6
Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis, file e0c31c08-1d4f-4599-e053-1705fe0aef77 5
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop, file e0c31c0a-3ad7-4599-e053-1705fe0aef77 5
A CFD-based simulation tool for the stability analysis of natural circulation systems, file e0c31c0e-d903-4599-e053-1705fe0aef77 5
On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error, file e0c31c12-4a03-4599-e053-1705fe0aef77 5
A laser heating study of the CeO2 solid/liquid transition: challenges related to a refractory compound with a very high oxygen pressure, file e0c31c07-be20-4599-e053-1705fe0aef77 4
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor, file e0c31c08-1def-4599-e053-1705fe0aef77 4
Development of the ALFRED reactor full power mode control system, file e0c31c09-54b7-4599-e053-1705fe0aef77 4
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS, file e0c31c0a-3b50-4599-e053-1705fe0aef77 4
Multi-physics tools development, file e0c31c0b-02b4-4599-e053-1705fe0aef77 4
Object-oriented modelling and simulation for the ALFRED dynamics, file e0c31c08-14e3-4599-e053-1705fe0aef77 3
A preliminary approach to the ALFRED reactor control strategy, file e0c31c08-19a8-4599-e053-1705fe0aef77 3
Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics, file e0c31c08-1d06-4599-e053-1705fe0aef77 3
The molten salt reactor (MSR) in generation IV: Overview and perspectives, file e0c31c08-1e2b-4599-e053-1705fe0aef77 3
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor, file e0c31c08-5d87-4599-e053-1705fe0aef77 3
Analytical and numerical investigation of the heat exchange effect on the dynamic behaviour of natural circulation with internally heated fluids, file e0c31c09-1fc1-4599-e053-1705fe0aef77 3
A Multi-Physics Modelling Approach to the Dynamics of Molten Salt Reactors, file e0c31c09-383d-4599-e053-1705fe0aef77 3
Improvement of the Control-Oriented Modelling of the GEN-IV Lead-Cooled Fast Reactor: Development of Reduced Order Methods, file e0c31c0a-4b66-4599-e053-1705fe0aef77 3
A reduced order model for investigating the dynamics of the Gen-IV LFR coolant pool, file e0c31c0a-4d20-4599-e053-1705fe0aef77 3
Thermal hydraulics of liquid-fueled MSRs, file e0c31c0a-f8c1-4599-e053-1705fe0aef77 3
Improved models of melting temperature and thermal conductivity for mixed oxide fuels doped with low minor actinide contents, file f4ebaf42-d062-4a67-8c8f-8800dc2da342 3
Dynamic stability of natural circulation loops for single phase fluids with internal heat generation, file e0c31c07-be2b-4599-e053-1705fe0aef77 2
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics, file e0c31c07-be76-4599-e053-1705fe0aef77 2
Modelling of Transient Fission Gas Behaviour in Oxide Fuel and Application to the BISON Code, file e0c31c07-be9f-4599-e053-1705fe0aef77 2
Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches, file e0c31c08-14e4-4599-e053-1705fe0aef77 2
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor, file e0c31c08-15c5-4599-e053-1705fe0aef77 2
On the melting behaviour of calcium monoxide under different atmospheres: A laser heating study, file e0c31c08-1713-4599-e053-1705fe0aef77 2
Totale 6839
Categoria #
all - tutte 8130
article - articoli 7454
book - libri 0
conference - conferenze 218
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 4
Totale 15806


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2017/201871 0055 25 319 14738
2018/2019319 5354 63 12 314711894
2019/20201006 79353074 6659 13099 13181109113
2020/20212072 10812211398 149338 160137 178204258207
2021/20222657 190206153232 245205 199185 301140370231
2022/2023683 1451553830 00 00 0000
Totale 6900