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

LORENZI, STEFANO
 Distribuzione geografica
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Continente #
NA - Nord America 12.955
EU - Europa 8.392
AS - Asia 6.828
SA - Sud America 1.211
AF - Africa 391
Continente sconosciuto - Info sul continente non disponibili 300
OC - Oceania 20
AN - Antartide 1
Totale 30.098
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Nazione #
US - Stati Uniti d'America 12.440
IT - Italia 3.145
RU - Federazione Russa 2.367
SG - Singapore 1.971
CN - Cina 1.632
BR - Brasile 961
VN - Vietnam 807
KR - Corea 700
FR - Francia 559
GB - Regno Unito 469
DE - Germania 361
JP - Giappone 355
NL - Olanda 310
CA - Canada 305
HK - Hong Kong 211
AT - Austria 198
IN - India 179
FI - Finlandia 167
BD - Bangladesh 133
JO - Giordania 131
ID - Indonesia 128
IE - Irlanda 124
TR - Turchia 123
MA - Marocco 121
SE - Svezia 116
MX - Messico 96
ES - Italia 90
CH - Svizzera 89
AR - Argentina 79
UA - Ucraina 79
BE - Belgio 70
IQ - Iraq 67
ZA - Sudafrica 66
PL - Polonia 52
TW - Taiwan 51
PK - Pakistan 50
EG - Egitto 49
IR - Iran 48
PH - Filippine 45
CZ - Repubblica Ceca 42
CO - Colombia 41
EC - Ecuador 36
DK - Danimarca 35
UZ - Uzbekistan 27
CI - Costa d'Avorio 25
CL - Cile 25
DZ - Algeria 24
NG - Nigeria 24
CR - Costa Rica 23
SA - Arabia Saudita 23
VE - Venezuela 23
JM - Giamaica 21
PY - Paraguay 21
AU - Australia 20
AE - Emirati Arabi Uniti 19
GR - Grecia 19
TH - Thailandia 19
RO - Romania 17
IL - Israele 16
KE - Kenya 15
EE - Estonia 14
TN - Tunisia 14
BO - Bolivia 13
BJ - Benin 12
HN - Honduras 12
KZ - Kazakistan 12
LT - Lituania 12
SI - Slovenia 12
LB - Libano 11
MY - Malesia 11
NI - Nicaragua 11
AZ - Azerbaigian 10
DO - Repubblica Dominicana 9
KG - Kirghizistan 9
PE - Perù 9
BG - Bulgaria 7
ET - Etiopia 7
PT - Portogallo 7
TT - Trinidad e Tobago 7
MU - Mauritius 6
OM - Oman 6
TZ - Tanzania 6
GT - Guatemala 5
HU - Ungheria 5
PA - Panama 5
PR - Porto Rico 5
SN - Senegal 5
SV - El Salvador 5
AM - Armenia 4
CY - Cipro 4
LC - Santa Lucia 4
LI - Liechtenstein 4
PS - Palestinian Territory 4
AL - Albania 3
BB - Barbados 3
GH - Ghana 3
KH - Cambogia 3
LK - Sri Lanka 3
LV - Lettonia 3
NO - Norvegia 3
Totale 29.747
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Città #
Ashburn 2.379
Milan 1.166
San Jose 1.146
Singapore 1.109
Santa Clara 800
Chandler 472
Fairfield 459
Council Bluffs 412
Seoul 402
Moscow 374
Woodbridge 331
Tokyo 314
Hefei 310
Houston 270
Seattle 247
The Dalles 247
Wilmington 233
Los Angeles 225
Dallas 223
Beijing 204
Ho Chi Minh City 202
Boardman 195
Vienna 185
Rome 182
Cambridge 169
Ann Arbor 167
Hanoi 159
Lauterbourg 157
Hong Kong 139
Amman 125
Phoenix 119
Dublin 117
London 117
New York 115
Ottawa 108
Columbus 100
São Paulo 99
Frankfurt am Main 94
Lawrence 94
Turin 90
Shanghai 88
North Charleston 87
Chicago 86
Delft 84
Redwood City 83
Dearborn 77
Kent 74
Helsinki 73
Medford 71
Orem 67
Amsterdam 62
Jakarta 62
Buffalo 60
Kenitra 56
Las Vegas 55
Dong Ket 54
Paris 51
Manchester 50
Montreal 49
Stockholm 49
Atlanta 48
Naples 46
San Diego 45
Casablanca 44
Bologna 43
Brussels 43
Da Nang 43
Guangzhou 42
Istanbul 39
Johannesburg 39
Brescia 38
Brooklyn 37
Redmond 37
Grenoble 36
Suwon 36
Nuremberg 35
Warsaw 35
Málaga 34
Rio de Janeiro 34
Belo Horizonte 33
Denver 33
Jacksonville 31
Miami 31
Toronto 31
Daejeon 30
Taipei 30
Haiphong 29
San Francisco 29
Zhengzhou 29
Chennai 28
Newark 28
Princeton 28
Düsseldorf 27
Zurich 27
Lappeenranta 25
Palermo 25
Prague 25
Shenzhen 25
Baghdad 24
Mumbai 24
Totale 16.740
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Nome #
Mass and Power Estimations of Moderated and Unmoderated HALEU Fueled Heat-Pipe Reactors for Space Applications 411
Description of initial reference design and identification of safety aspects 396
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 350
Development of a control-oriented power plant simulator for the molten salt fast reactor 347
Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor 345
Development of best estimate numerical tools for LFR design and safety analysis 339
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project 323
Dynamics in natural circulation loop for internally heated molten salt 317
1D Modelica Modeling of the DYNASTY-eDYNASTY Coupled Natural Circulation Loops 307
Mass and Power Scaling of HALEU Fueled Heat-Pipe Nuclear Reactors for Selected Lunar Base scenarios 292
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants 288
OpenMC Analysis of TRIGA Mark II Reactor Void and Temperature Reactivity Coefficients 282
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR 276
ALFRED reactor and hybrid systems: A test case 271
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor 267
Development of an OpenFOAM multiphysics solver for solid fission products transport in the Molten Salt Fast Reactor 266
Flow pattern visualization and definition of transition criteria for two-phase flow in Chevron-type corrugated channels 262
Dynamics of Natural Circulation in Presence of Distributed Heating: Results of the SAMOFAR CFD Simulation Campaign 261
Numerical methodology for design and evaluation of natural circulation systems for MSR applications 260
Neutron Flux Reconstruction from Out-Core Sparse Measurements using Data-Driven Reduced Order Modelling 258
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 257
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 250
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 246
Development of a control-oriented simulator for a LFR demonstrator 245
Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation 245
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response 244
Dynamic Mode Decomposition for the Control of Nuclear Power Plants 242
Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor 241
A 3D CFD Model for the Study of Natural Circulation in the Pavia TRIGA Mark II Research Reactor 234
A Serpent/OpenFOAM coupling approach for the study of the fuel burnup 231
A CFD-based simulation tool for the stability analysis of natural circulation systems 230
1D modelling and preliminary analysis of the coupled DYNASTY–eDYNASTY natural circulation loop 225
Instabilities of burnup calculations in a SERPENT/OPENFOAM coupling 225
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor 224
Nuovo nucleare: Small Modular Reactors e sistemi energetici ibridi 221
A preliminary approach to the ALFRED reactor control strategy 220
A Reduced Order Kalman Filter for Computational Fluid-Dynamics Applications 216
A comprehensive methodology for designing a nuclear electric propulsion (NEP) concept 216
Modeling and simulation of nuclear hybrid energy systems architectures 214
Complete Thermal-Hydraulic Modelling of the Pavia TRIGA Mark II Research Reactor for the Study of the Natural Circulation Regime 212
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches 212
Sub-channel thermal hydraulics analysis of the 250 kW TRIGA Mark II nuclear reactor 210
Small modular reactors: economic, safety, and environmental aspects 209
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts 208
Multiphysics modelling of gaseous fission products in the Molten Salt Fast Reactor 208
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor 205
Development of the ALFRED reactor full power mode control system 205
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor 204
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 204
A multi-physics modelling approach for the analysis of Lead Fast Reactors 203
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 202
Advanced Modelling And Stability Analysis For Nuclear Reactors 202
Dynamic modelling and optimisation of a Small Modular Reactor for electricity production and district heating in the Helsinki region 200
Object-oriented modelling and simulation for the ALFRED dynamics 199
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events 198
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 2 : Application and Results 198
ANALYSIS OF THE COOLANT DENSITY REACTIVITY COEFFICIENT IN LFRs AND SFRs VIA MONTE CARLO PERTURBATION/SENSITIVITY 197
Derivation and Implementation in OpenFOAM of a Point-Kinetics Model for Molten Salt Reactors 196
A mass conservative Kalman filter algorithm for computational thermo-fluid dynamics 195
A New Reactivity Control Approach for Circulating Fuel Reactors 195
Modelling and CFD analysis of the DYNASTY loop facility 194
Analytical models for a small LFR core dynamics studies 194
On the need for multi-dimensional models for the safety analysis of (fast-spectrum) Molten Salt Reactors 192
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 1: Numerical Modelling 191
A coupled neutronic and thermal-hydraulic model for ALFRED 189
Multi-physics tools development 188
Analysis of KRUSTY reactor behaviour with OFELIA environment 186
Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core 186
An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purposes 186
A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset 185
A multiphysics model for analysis of inert gas bubbles in Molten Salt Fast Reactor 183
Improvement of the Control-Oriented Modelling of the GEN-IV Lead-Cooled Fast Reactor: Development of Reduced Order Methods 182
Large Eddy Simulation of the Dynamic Behaviour of the Dynasty Natural Circulation Loop 181
A Data-driven Incident Detection Method for the Safe Operation of Molten Salt Fast Reactors 180
Multiphysics analysis of RANS-based turbulent transport of solid fission products in the Molten Salt Fast Reactor 180
Effects of a multi-physics coupling approach in Monte Carlo burnup calculations 179
Reduced order modeling approach for parametrized thermal-hydraulics problems: inclusion of the energy equation in the POD-FV-ROM method 179
Development of a Data-Driven Approach Based on Kalman Filtering for CFD Reactor Analysis 177
Preliminary analysis and design of the energy conversion system for the molten salt fast reactor 175
Economics and finance of lead fast reactors: A systematic literature review 174
Petri-net based modelling approach for ALFRED reactor operation and control system design 174
Preliminary validation of the 1D modeling of the DYNASTY natural circulation loop against results from water experimental campaign 173
IAEA INITIATIVE ON OPEN-SOURCE NUCLEAR CODES FOR REACTOR ANALYSIS 172
A Serpent/OpenFOAM coupling for 3D burnup analysis 171
An Adjoint Proper Orthogonal Decomposition method for a neutronics reduced order model 170
Linear Stability Analysis of a Heated Channel in the Supercritical Water Reactor 169
Object-oriented modeling, simulation and control of a 6-DoF parallel kinematic manipulator for remote handling in DONES facility 168
Stability analysis on two single-phase coupled natural circulation loops 167
Adaptive simulation for failure identification in the Advanced Lead Fast Reactor European Demonstrator 167
Stability analyses for the European LFR demonstrator 163
Sensitivity And Uncertainty Analysis of the TRIGA Mark II Reactor Using First and Second Order Perturbation Theory 163
Non-intrusive system state reconstruction from indirect measurements: A novel approach based on Hybrid Data Assimilation methods 162
Modelling of the DYNASTY experimental facility for natural circulation under distributed heating 161
Evaluation of the Coolant Reactivity Coefficient Influence on the Dynamic Response of a Small LFR System 161
Hybrid data assimilation methods, Part I: Numerical comparison between GEIM and PBDW 160
Safety Issues Affecting the Feasibility of an Early High-Flux LFR Technology Demonstrator 160
An intrinsically safe facility for forefront research and training on nuclear technologies — Kinetics and dynamics 159
Hybrid Data Assimilation methods: application to the DYNASTY experimental facility 158
Challenges regarding the Experimental Validation of Thermal-Hydraulic Modeling Tools for a European SMR 158
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 157
Totale 21.780
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Categoria #
all - tutte 81.247
article - articoli 41.614
book - libri 0
conference - conferenze 34.157
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 351
Totale 157.369
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/2022704 0 0 0 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
2026/20273.295 577 742 1.203 773 0 0 0 0 0 0 0 0
Totale 30.098