LUZZI, LELIO
 Distribuzione geografica
Continente #
EU - Europa 5.809
NA - Nord America 4.445
AS - Asia 2.509
AF - Africa 265
SA - Sud America 131
OC - Oceania 54
Continente sconosciuto - Info sul continente non disponibili 4
Totale 13.217
Nazione #
US - Stati Uniti d'America 4.131
IT - Italia 2.394
CN - Cina 725
FR - Francia 715
GB - Regno Unito 406
TR - Turchia 318
DE - Germania 315
RU - Federazione Russa 311
CA - Canada 247
NL - Olanda 241
JP - Giappone 221
IN - India 196
IR - Iran 196
KR - Corea 195
CZ - Repubblica Ceca 177
DK - Danimarca 175
ID - Indonesia 138
AT - Austria 136
RO - Romania 125
CH - Svizzera 121
EG - Egitto 121
HK - Hong Kong 105
UA - Ucraina 94
SE - Svezia 86
VN - Vietnam 82
BE - Belgio 74
ES - Italia 74
PL - Polonia 67
BR - Brasile 65
TW - Taiwan 55
ZA - Sudafrica 48
DZ - Algeria 47
HU - Ungheria 46
SG - Singapore 44
MX - Messico 43
GR - Grecia 42
AU - Australia 40
FI - Finlandia 34
BD - Bangladesh 33
HR - Croazia 33
AE - Emirati Arabi Uniti 32
AR - Argentina 32
PK - Pakistan 30
IE - Irlanda 27
CL - Cile 22
IQ - Iraq 22
TH - Thailandia 21
IL - Israele 17
NO - Norvegia 17
BG - Bulgaria 15
PT - Portogallo 15
SA - Arabia Saudita 15
MY - Malesia 14
MA - Marocco 13
SK - Slovacchia (Repubblica Slovacca) 13
LT - Lituania 12
NZ - Nuova Zelanda 12
JO - Giordania 11
SI - Slovenia 11
SC - Seychelles 10
HN - Honduras 9
AF - Afghanistan, Repubblica islamica di 8
LU - Lussemburgo 8
RS - Serbia 8
BZ - Belize 7
EE - Estonia 7
UZ - Uzbekistan 6
MN - Mongolia 5
PH - Filippine 5
CM - Camerun 4
CO - Colombia 4
LY - Libia 4
BO - Bolivia 3
BT - Bhutan 3
EU - Europa 3
GH - Ghana 3
LV - Lettonia 3
NG - Nigeria 3
SY - Repubblica araba siriana 3
TN - Tunisia 3
VE - Venezuela 3
AL - Albania 2
AM - Armenia 2
BA - Bosnia-Erzegovina 2
JM - Giamaica 2
MZ - Mozambico 2
NP - Nepal 2
PS - Palestinian Territory 2
RW - Ruanda 2
SV - El Salvador 2
UG - Uganda 2
A2 - ???statistics.table.value.countryCode.A2??? 1
BW - Botswana 1
CG - Congo 1
CR - Costa Rica 1
CU - Cuba 1
EC - Ecuador 1
FJ - Figi 1
IS - Islanda 1
KE - Kenya 1
Totale 13.208
Città #
Milan 678
Ashburn 266
Fairfield 248
Buffalo 177
Santa Cruz 172
Houston 162
Istanbul 156
Seattle 152
Jinan 150
Rome 133
Vienna 113
Woodbridge 110
Cambridge 105
Paris 95
Chicago 92
Turin 88
Wilmington 84
Los Angeles 78
Ann Arbor 69
Moscow 66
Copenhagen 65
Tokyo 64
Shanghai 60
Boardman 59
Guangzhou 57
Ankara 51
Bucharest 51
Bologna 45
Manchester 45
Council Bluffs 42
Gif-sur-yvette 42
London 42
Phoenix 42
Redmond 42
College Station 41
Amsterdam 39
Dong Ket 39
Ottawa 39
Budapest 38
Cairo 38
Dallas 38
Las Vegas 36
Henderson 35
Tortona 35
Atlanta 33
Delft 33
New York 33
Jakarta 32
Beijing 31
Idaho Falls 31
Lausanne 30
Mumbai 30
Prague 30
Seoul 30
Torino 30
Kitchener 29
Toronto 29
Mountain View 28
Santa Clara 28
Taipei 28
Madison 27
Tehran 27
Zagreb 27
Genoa 25
San Diego 25
Muizenberg 24
Shenyang 24
Fleming Island 23
Grenoble 23
Marseille 23
Norwalk 23
Lancaster 22
Clearwater 21
Frederiksberg 21
Karlsruhe 21
Knoxville 21
Raleigh 21
Dublin 20
Heerenveen 20
Tianjin 20
Pisa 19
Richmond 19
San Jose 19
Bengaluru 18
Central 18
Hangzhou 18
Lyon 18
Madrid 18
Naples 18
Pembroke 18
Warsaw 18
Xian 18
Abbiategrasso 17
Brussels 17
Harbin 17
Munich 17
Bresso 16
Rotterdam 16
Shenzhen 16
Stockholm 16
Totale 5.573
Nome #
The molten salt reactor (MSR) in generation IV: Overview and perspectives, file e0c31c0d-6a55-4599-e053-1705fe0aef77 2.214
Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches, file e0c31c0d-c0f8-4599-e053-1705fe0aef77 1.358
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor, file e0c31c0d-8364-4599-e053-1705fe0aef77 815
Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis, file e0c31c0d-2fb9-4599-e053-1705fe0aef77 624
Fuel Modelling in Accident Conditions (FUMAC), file e0c31c0e-fee8-4599-e053-1705fe0aef77 619
Modelling and analysis of the MSFR transient behaviour, file e0c31c0d-d7dc-4599-e053-1705fe0aef77 436
DarkSide-20k Preliminary Design Report: The Global Argon Dark Matter Collaboration, file e0c31c11-287f-4599-e053-1705fe0aef77 374
A preliminary approach to the ALFRED reactor control strategy, file e0c31c0d-66e1-4599-e053-1705fe0aef77 369
Object-oriented modelling and simulation for the ALFRED dynamics, file e0c31c0d-6393-4599-e053-1705fe0aef77 327
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects, file e0c31c0c-e3e6-4599-e053-1705fe0aef77 311
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics, file e0c31c0e-779f-4599-e053-1705fe0aef77 281
Dynamic stability of natural circulation loops for single phase fluids with internal heat generation, file e0c31c0e-6273-4599-e053-1705fe0aef77 236
Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling, file e0c31c0e-7d2c-4599-e053-1705fe0aef77 224
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations, file e0c31c11-269a-4599-e053-1705fe0aef77 217
Vaporization behaviour of a PuF3-containing fuel mixture for the Molten Salt Fast Reactor, file e0c31c0f-346e-4599-e053-1705fe0aef77 206
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor, file e0c31c0d-1f54-4599-e053-1705fe0aef77 200
Vaporization behaviour of the Molten Salt Fast Reactor fuel: The LiF-ThF4-UF4 system, file e0c31c0b-f8b3-4599-e053-1705fe0aef77 176
Synthesis of plutonium trifluoride by hydro-fluorination and novel thermodynamic data for the PuF3-LiF system, file e0c31c0b-c09f-4599-e053-1705fe0aef77 162
Innovative preparation route for uranium carbide using citric acid as a carbon source, file e0c31c09-cecb-4599-e053-1705fe0aef77 151
The solidification behaviour of the UO2-ThO2 system in a laser heating study, file e0c31c08-1e6f-4599-e053-1705fe0aef77 149
Development of the ALFRED reactor full power mode control system, file e0c31c0e-77a0-4599-e053-1705fe0aef77 149
Final report on rod cladding failure during SGTR, file eedd6d35-ee8e-41eb-a9f7-a64f0d904d50 149
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 146
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 146
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor, file e0c31c0c-7580-4599-e053-1705fe0aef77 141
The Role of Italian universities/CIRTEN for the engineering study of a fission-fusion hybrid reactor (FFHR), file e0c31c0a-7b8f-4599-e053-1705fe0aef77 140
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools, file e0c31c0c-1c20-4599-e053-1705fe0aef77 134
DarkSide-20k: A 20 tonne two-phase LAr TPC for direct dark matter detection at LNGS, file e0c31c0f-ff4d-4599-e053-1705fe0aef77 125
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS, file e0c31c0f-3db2-4599-e053-1705fe0aef77 123
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 122
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations, file e0c31c0b-9f7d-4599-e053-1705fe0aef77 119
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant, file e0c31c0c-8282-4599-e053-1705fe0aef77 109
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources, file e0c31c0a-38b1-4599-e053-1705fe0aef77 108
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 108
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor, file e0c31c08-1ec8-4599-e053-1705fe0aef77 107
Microhardness and Young's modulus of high burn-up UO2 fuel, file e0c31c09-bec0-4599-e053-1705fe0aef77 103
Spark plasma sintering of fine uranium carbide powder, file e0c31c09-fb14-4599-e053-1705fe0aef77 97
On the melting behaviour of calcium monoxide under different atmospheres: A laser heating study, file e0c31c0d-ead1-4599-e053-1705fe0aef77 92
Development of best estimate numerical tools for LFR design and safety analysis, file e0c31c11-2334-4599-e053-1705fe0aef77 85
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions, file e0c31c12-7f7d-4599-e053-1705fe0aef77 84
High-temperature and melting behaviour of nanocrystalline refractory compounds: an experimental approach applied to thorium dioxide, file e0c31c07-bdd7-4599-e053-1705fe0aef77 77
Report on the improved models of melting temperature and thermal conductivity for MOX fuels and JOG, file e0c31c11-0a0c-4599-e053-1705fe0aef77 75
Design and construction of a new detector to measure ultra-low radioactive-isotope contamination of argon, file e0c31c0f-6f93-4599-e053-1705fe0aef77 74
Incorporation and verification of models and properties in fuel performance codes, file e0c31c11-3282-4599-e053-1705fe0aef77 74
A preliminary approach to the MSFR control issues, file e0c31c0d-a8d6-4599-e053-1705fe0aef77 72
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients, file e0c31c10-072f-4599-e053-1705fe0aef77 72
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor, file e0c31c0e-77a7-4599-e053-1705fe0aef77 66
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 63
Isobaric heat capacity of solid and liquid thorium tetrafluoride, file e0c31c0f-2e56-4599-e053-1705fe0aef77 61
Report describing the irradiation experiments selected for the assessment of fuel performance codes, file e0c31c11-43a5-4599-e053-1705fe0aef77 60
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment, file e0c31c11-66e1-4599-e053-1705fe0aef77 57
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 56
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications, file e0c31c0f-a502-4599-e053-1705fe0aef77 53
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 46
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor, file e0c31c0e-83ce-4599-e053-1705fe0aef77 42
Laser melting of nano-crystalline uranium dioxide, file e0c31c0d-6892-4599-e053-1705fe0aef77 40
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX, file 349fe6f6-fa64-44f8-aec3-7a8681055a88 38
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part II: Coupling SCIANTIX with TRANSURANUS, file d13d261f-9f9a-4562-8111-6b2968efa829 38
Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions, file 4a4c0296-13dc-4e2c-b862-41e38364b1b6 34
Improved models of melting temperature and thermal conductivity for mixed oxide fuels doped with low minor actinide contents, file f4ebaf42-d062-4a67-8c8f-8800dc2da342 32
Synthesis of INSPYRE results, file d48a7793-5d73-4d02-95c2-ff437496291b 30
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment, file e7e10bd5-806d-4a25-bb59-2875e7d449d7 30
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution, file e0c31c12-87ff-4599-e053-1705fe0aef77 27
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 27
Synthesis of the presentation of INSPYRE results to the User Group, file 9a0544ca-5818-490a-85d3-5a4c8b737046 26
Results of the applicative benchmark between TRANSURANUS and GERMINAL on the ASTRID case study, file e0c31c11-5faa-4599-e053-1705fe0aef77 26
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 25
Synthesis of the inert gas behaviour models developed in INSPYRE, file e0c31c11-000c-4599-e053-1705fe0aef77 24
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor, file e0c31c11-f94e-4599-e053-1705fe0aef77 24
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 21
Fuel performance simulations of ESNII prototypes: Results on the MYRRHA case study, file 67e60494-3ef6-499b-8963-3f77d2331374 20
SiPM-matrix readout of two-phase argon detectors using electroluminescence in the visible and near infrared range, file e0c31c11-2bf9-4599-e053-1705fe0aef77 20
Simulation of the Melting Behavior of the UO2-Zircaloy Fuel Cladding System by Laser Heating, file 38e09468-c997-40f3-ab61-818ae4e4f0aa 18
A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes, file e0c31c12-890d-4599-e053-1705fe0aef77 18
Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX, file 51c36818-c26d-4300-b58e-37b5bc8c7a52 16
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 16
Results of the benchmark between pre- and post-INSPYRE code versions on selected experimental cases, file fbc03e51-510d-4843-8083-35c8f07eddb4 14
Synthesis of the First User Group Meeting, file e0c31c11-000a-4599-e053-1705fe0aef77 13
Description of new meso-scale models and their implementation in fuel performance codes, file f6e82746-a87a-47b7-83bf-d9526b4bc972 11
Cryogenic Characterization of FBK RGB-HD SiPMs, file e0c31c0b-88d1-4599-e053-1705fe0aef77 10
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor, file e0c31c0c-de49-4599-e053-1705fe0aef77 10
Third Yearly Activity Report, file 0c5e3fa9-5fbd-42e1-9cb8-2743db035309 9
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
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System, file e0c31c0d-432c-4599-e053-1705fe0aef77 9
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 9
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events, file e0c31c0c-fcc9-4599-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
Towards multi-physics description of fuel behaviour for accidental conditions, file 0c5511c1-ac74-4094-926f-0b879e7fbf96 5
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
A surrogate model for the helium production rate in fast reactor MOX fuels, file 1888f666-30df-4998-9078-06f8d76bfe67 4
A modelling methodology for the description of helium behaviour accounting for the grain-size distribution, file 24714dd1-5353-40ed-89b1-d8ad52be28bc 4
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F, file a6d0aca8-8468-4fbb-bb76-009d1762af4e 4
Best practices and QA protocols for code development, file c4e790d9-b3ed-40f8-999d-9fa78dd49637 4
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
Totale 13.504
Categoria #
all - tutte 25.645
article - articoli 22.827
book - libri 0
conference - conferenze 555
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 4
Totale 49.031


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2018/2019290 0 0 0 0 0 0 0 0 31 47 118 94
2019/20201.006 79 35 30 74 66 59 130 99 131 81 109 113
2020/20212.072 108 122 113 98 149 338 160 137 178 204 258 207
2021/20222.657 190 206 153 232 245 205 199 185 301 140 370 231
2022/20233.806 145 155 430 278 307 249 343 386 332 430 356 395
2023/20243.608 362 340 398 393 456 354 476 477 352 0 0 0
Totale 13.631