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

LORENZI, STEFANO
 Distribuzione geografica
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Continente #
NA - Nord America 10.950
EU - Europa 8.008
AS - Asia 6.716
SA - Sud America 1.179
AF - Africa 380
Continente sconosciuto - Info sul continente non disponibili 300
OC - Oceania 20
AN - Antartide 1
Totale 27.554
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Nazione #
US - Stati Uniti d'America 10.517
IT - Italia 2.881
RU - Federazione Russa 2.366
SG - Singapore 1.964
CN - Cina 1.613
BR - Brasile 946
VN - Vietnam 805
KR - Corea 671
FR - Francia 548
GB - Regno Unito 441
DE - Germania 346
JP - Giappone 344
NL - Olanda 296
CA - Canada 263
HK - Hong Kong 209
AT - Austria 197
IN - India 175
FI - Finlandia 166
BD - Bangladesh 132
JO - Giordania 131
IE - Irlanda 123
ID - Indonesia 118
MA - Marocco 117
TR - Turchia 115
SE - Svezia 96
MX - Messico 93
ES - Italia 86
CH - Svizzera 84
UA - Ucraina 79
AR - Argentina 74
BE - Belgio 68
IQ - Iraq 66
ZA - Sudafrica 65
TW - Taiwan 51
PK - Pakistan 50
EG - Egitto 49
PL - Polonia 48
IR - Iran 45
PH - Filippine 44
CZ - Repubblica Ceca 41
EC - Ecuador 35
CO - Colombia 33
DK - Danimarca 30
UZ - Uzbekistan 27
CI - Costa d'Avorio 25
NG - Nigeria 24
CL - Cile 23
DZ - Algeria 22
SA - Arabia Saudita 22
VE - Venezuela 22
PY - Paraguay 21
AU - Australia 20
GR - Grecia 19
AE - Emirati Arabi Uniti 17
RO - Romania 17
JM - Giamaica 16
KE - Kenya 15
CR - Costa Rica 14
IL - Israele 14
TH - Thailandia 14
BO - Bolivia 13
TN - Tunisia 13
BJ - Benin 12
KZ - Kazakistan 12
LT - Lituania 12
SI - Slovenia 12
LB - Libano 11
AZ - Azerbaigian 9
DO - Repubblica Dominicana 9
KG - Kirghizistan 9
MY - Malesia 9
PE - Perù 9
BG - Bulgaria 7
EE - Estonia 7
ET - Etiopia 7
PT - Portogallo 7
MU - Mauritius 6
NI - Nicaragua 6
OM - Oman 6
TZ - Tanzania 6
HN - Honduras 5
HU - Ungheria 5
PA - Panama 5
SN - Senegal 5
TT - Trinidad e Tobago 5
AM - Armenia 4
CY - Cipro 4
GT - Guatemala 4
LI - Liechtenstein 4
PS - Palestinian Territory 4
AL - Albania 3
GH - Ghana 3
KH - Cambogia 3
LK - Sri Lanka 3
LV - Lettonia 3
NO - Norvegia 3
NP - Nepal 3
QA - Qatar 3
SV - El Salvador 3
BB - Barbados 2
Totale 27.209
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Città #
Ashburn 1.826
Singapore 1.109
Milan 1.101
San Jose 931
Santa Clara 765
Chandler 472
Fairfield 459
Seoul 401
Moscow 374
Woodbridge 331
Hefei 310
Council Bluffs 309
Tokyo 307
Houston 263
Seattle 246
The Dalles 241
Wilmington 231
Ho Chi Minh City 202
Beijing 199
Dallas 197
Los Angeles 196
Boardman 195
Vienna 184
Cambridge 168
Ann Arbor 167
Hanoi 159
Lauterbourg 157
Rome 157
Hong Kong 138
Amman 125
Dublin 116
London 115
Ottawa 107
New York 101
Columbus 98
Lawrence 94
São Paulo 94
Frankfurt am Main 93
North Charleston 87
Shanghai 87
Turin 85
Delft 84
Redwood City 83
Dearborn 77
Kent 74
Helsinki 73
Medford 71
Chicago 69
Orem 64
Jakarta 62
Buffalo 57
Kenitra 56
Amsterdam 54
Dong Ket 54
Manchester 49
Stockholm 49
Las Vegas 48
Paris 48
Casablanca 44
Montreal 44
Brussels 43
Da Nang 42
Guangzhou 42
San Diego 42
Bologna 39
Johannesburg 39
Naples 38
Brescia 37
Redmond 37
Istanbul 36
Suwon 36
Nuremberg 35
Phoenix 35
Grenoble 34
Málaga 34
Rio de Janeiro 33
Warsaw 32
Atlanta 31
Belo Horizonte 30
Taipei 30
Haiphong 29
Jacksonville 29
Zhengzhou 29
Brooklyn 28
Denver 28
Princeton 28
Chennai 27
Düsseldorf 27
Miami 27
Toronto 27
Zurich 27
Lappeenranta 25
Prague 25
Shenzhen 25
Baghdad 24
Daejeon 24
Mumbai 24
Ankara 23
Palermo 23
Abidjan 22
Totale 15.403
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Nome #
Description of initial reference design and identification of safety aspects 355
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 344
Development of a control-oriented power plant simulator for the molten salt fast reactor 337
Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor 331
Development of best estimate numerical tools for LFR design and safety analysis 329
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project 313
Mass and Power Estimations of Moderated and Unmoderated HALEU Fueled Heat-Pipe Reactors for Space Applications 311
Dynamics in natural circulation loop for internally heated molten salt 286
1D Modelica Modeling of the DYNASTY-eDYNASTY Coupled Natural Circulation Loops 282
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants 268
OpenMC Analysis of TRIGA Mark II Reactor Void and Temperature Reactivity Coefficients 262
Mass and Power Scaling of HALEU Fueled Heat-Pipe Nuclear Reactors for Selected Lunar Base scenarios 259
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor 257
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR 253
Numerical methodology for design and evaluation of natural circulation systems for MSR applications 251
Development of an OpenFOAM multiphysics solver for solid fission products transport in the Molten Salt Fast Reactor 250
Dynamics of Natural Circulation in Presence of Distributed Heating: Results of the SAMOFAR CFD Simulation Campaign 249
ALFRED reactor and hybrid systems: A test case 246
Flow pattern visualization and definition of transition criteria for two-phase flow in Chevron-type corrugated channels 246
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 244
Neutron Flux Reconstruction from Out-Core Sparse Measurements using Data-Driven Reduced Order Modelling 239
Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation 239
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 238
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response 236
Development of a control-oriented simulator for a LFR demonstrator 235
Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor 234
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 230
Dynamic Mode Decomposition for the Control of Nuclear Power Plants 228
A CFD-based simulation tool for the stability analysis of natural circulation systems 219
A preliminary approach to the ALFRED reactor control strategy 216
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor 215
A Serpent/OpenFOAM coupling approach for the study of the fuel burnup 212
1D modelling and preliminary analysis of the coupled DYNASTY–eDYNASTY natural circulation loop 206
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches 205
Sub-channel thermal hydraulics analysis of the 250 kW TRIGA Mark II nuclear reactor 204
A 3D CFD Model for the Study of Natural Circulation in the Pavia TRIGA Mark II Research Reactor 203
A Reduced Order Kalman Filter for Computational Fluid-Dynamics Applications 203
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts 200
Nuovo nucleare: Small Modular Reactors e sistemi energetici ibridi 199
Instabilities of burnup calculations in a SERPENT/OPENFOAM coupling 196
Modeling and simulation of nuclear hybrid energy systems architectures 196
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 195
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 194
Development of the ALFRED reactor full power mode control system 193
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events 193
Object-oriented modelling and simulation for the ALFRED dynamics 191
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor 191
Advanced Modelling And Stability Analysis For Nuclear Reactors 191
Dynamic modelling and optimisation of a Small Modular Reactor for electricity production and district heating in the Helsinki region 189
A comprehensive methodology for designing a nuclear electric propulsion (NEP) concept 188
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor 186
On the need for multi-dimensional models for the safety analysis of (fast-spectrum) Molten Salt Reactors 185
Analytical models for a small LFR core dynamics studies 185
A mass conservative Kalman filter algorithm for computational thermo-fluid dynamics 184
Complete Thermal-Hydraulic Modelling of the Pavia TRIGA Mark II Research Reactor for the Study of the Natural Circulation Regime 183
Derivation and Implementation in OpenFOAM of a Point-Kinetics Model for Molten Salt Reactors 182
Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core 181
A New Reactivity Control Approach for Circulating Fuel Reactors 181
A multi-physics modelling approach for the analysis of Lead Fast Reactors 180
Modelling and CFD analysis of the DYNASTY loop facility 179
A coupled neutronic and thermal-hydraulic model for ALFRED 179
Multiphysics modelling of gaseous fission products in the Molten Salt Fast Reactor 178
An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purposes 177
Development of a Data-Driven Approach Based on Kalman Filtering for CFD Reactor Analysis 173
A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset 172
ANALYSIS OF THE COOLANT DENSITY REACTIVITY COEFFICIENT IN LFRs AND SFRs VIA MONTE CARLO PERTURBATION/SENSITIVITY 172
Multi-physics tools development 171
A multiphysics model for analysis of inert gas bubbles in Molten Salt Fast Reactor 171
Analysis of KRUSTY reactor behaviour with OFELIA environment 170
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 2 : Application and Results 170
A Data-driven Incident Detection Method for the Safe Operation of Molten Salt Fast Reactors 169
Large Eddy Simulation of the Dynamic Behaviour of the Dynasty Natural Circulation Loop 168
Improvement of the Control-Oriented Modelling of the GEN-IV Lead-Cooled Fast Reactor: Development of Reduced Order Methods 165
Petri-net based modelling approach for ALFRED reactor operation and control system design 163
An Adjoint Proper Orthogonal Decomposition method for a neutronics reduced order model 163
Effects of a multi-physics coupling approach in Monte Carlo burnup calculations 163
Reduced order modeling approach for parametrized thermal-hydraulics problems: inclusion of the energy equation in the POD-FV-ROM method 163
Multiphysics analysis of RANS-based turbulent transport of solid fission products in the Molten Salt Fast Reactor 163
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 1: Numerical Modelling 162
IAEA INITIATIVE ON OPEN-SOURCE NUCLEAR CODES FOR REACTOR ANALYSIS 159
Preliminary analysis and design of the energy conversion system for the molten salt fast reactor 158
A Serpent/OpenFOAM coupling for 3D burnup analysis 157
Adaptive simulation for failure identification in the Advanced Lead Fast Reactor European Demonstrator 156
Evaluation of the Coolant Reactivity Coefficient Influence on the Dynamic Response of a Small LFR System 155
Stability analyses for the European LFR demonstrator 155
Linear Stability Analysis of a Heated Channel in the Supercritical Water Reactor 154
Preliminary validation of the 1D modeling of the DYNASTY natural circulation loop against results from water experimental campaign 153
Non-intrusive system state reconstruction from indirect measurements: A novel approach based on Hybrid Data Assimilation methods 153
Economics and finance of lead fast reactors: A systematic literature review 152
Hybrid Data Assimilation methods: application to the DYNASTY experimental facility 150
Hybrid data assimilation methods, Part I: Numerical comparison between GEIM and PBDW 149
Development of best estimate numerical tools for LFR design and safety analysis 149
Modelling of the DYNASTY experimental facility for natural circulation under distributed heating 148
Safety Issues Affecting the Feasibility of an Early High-Flux LFR Technology Demonstrator 148
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 148
An intrinsically safe facility for forefront research and training on nuclear technologies — Kinetics and dynamics 147
Preliminary results of the experimental campaign conducted on the DYNASTY natural circulation loop 145
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System 142
A reduced order model for fission gas diffusion in columnar grains 142
Object-oriented modeling, simulation and control of a 6-DoF parallel kinematic manipulator for remote handling in DONES facility 141
Totale 20.150
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Categoria #
all - tutte 74.928
article - articoli 38.656
book - libri 0
conference - conferenze 31.270
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 246
Totale 145.100
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/2022814 0 68 42 41 62 49 59 83 77 89 96 148
2022/20231.993 138 158 74 132 168 345 72 162 359 102 173 110
2023/20241.621 94 167 124 138 94 122 165 162 47 126 195 187
2024/20254.490 87 121 140 108 797 505 289 335 615 327 565 601
2025/202613.935 1.977 1.947 748 1.076 795 680 1.955 944 991 1.300 535 987
2026/2027751 577 174 0 0 0 0 0 0 0 0 0 0
Totale 27.554