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

LORENZI, STEFANO
 Distribuzione geografica
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Continente #
NA - Nord America 9.783
EU - Europa 7.056
AS - Asia 6.539
SA - Sud America 1.157
AF - Africa 369
OC - Oceania 20
Continente sconosciuto - Info sul continente non disponibili 2
AN - Antartide 1
Totale 24.927
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Nazione #
US - Stati Uniti d'America 9.422
RU - Federazione Russa 2.366
IT - Italia 2.077
SG - Singapore 1.952
CN - Cina 1.592
BR - Brasile 935
VN - Vietnam 769
KR - Corea 659
FR - Francia 522
GB - Regno Unito 407
JP - Giappone 339
DE - Germania 310
NL - Olanda 279
CA - Canada 228
AT - Austria 197
HK - Hong Kong 195
FI - Finlandia 166
IN - India 165
JO - Giordania 131
IE - Irlanda 123
MA - Marocco 117
ID - Indonesia 115
TR - Turchia 113
SE - Svezia 93
MX - Messico 88
ES - Italia 85
UA - Ucraina 79
BD - Bangladesh 72
CH - Svizzera 72
AR - Argentina 71
IQ - Iraq 66
ZA - Sudafrica 65
BE - Belgio 60
TW - Taiwan 51
PK - Pakistan 49
EG - Egitto 48
PL - Polonia 46
IR - Iran 44
PH - Filippine 44
CZ - Repubblica Ceca 41
EC - Ecuador 34
CO - Colombia 31
UZ - Uzbekistan 27
DK - Danimarca 26
CI - Costa d'Avorio 25
DZ - Algeria 22
SA - Arabia Saudita 22
CL - Cile 21
PY - Paraguay 21
VE - Venezuela 21
AU - Australia 20
GR - Grecia 19
AE - Emirati Arabi Uniti 17
RO - Romania 16
KE - Kenya 15
IL - Israele 14
NG - Nigeria 14
TH - Thailandia 14
TN - Tunisia 13
BJ - Benin 12
BO - Bolivia 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
CR - Costa Rica 8
BG - Bulgaria 7
EE - Estonia 7
ET - Etiopia 7
JM - Giamaica 7
PT - Portogallo 7
MU - Mauritius 6
OM - Oman 6
TZ - Tanzania 6
PA - Panama 5
SN - Senegal 5
AM - Armenia 4
CY - Cipro 4
HU - Ungheria 4
LI - Liechtenstein 4
NI - Nicaragua 4
PS - Palestinian Territory 4
AL - Albania 3
GH - Ghana 3
KH - Cambogia 3
LK - Sri Lanka 3
LV - Lettonia 3
NP - Nepal 3
QA - Qatar 3
TT - Trinidad e Tobago 3
BW - Botswana 2
GE - Georgia 2
HN - Honduras 2
KW - Kuwait 2
MT - Malta 2
Totale 24.890
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Città #
Ashburn 1.684
Singapore 1.102
San Jose 834
Milan 827
Santa Clara 737
Chandler 472
Fairfield 459
Seoul 398
Moscow 374
Woodbridge 331
Hefei 310
Tokyo 305
Council Bluffs 263
Houston 256
Seattle 246
The Dalles 237
Wilmington 231
Beijing 193
Ho Chi Minh City 186
Vienna 184
Los Angeles 178
Dallas 174
Ann Arbor 167
Cambridge 165
Lauterbourg 157
Boardman 151
Hanoi 149
Hong Kong 129
Amman 125
London 115
Dublin 114
Ottawa 106
Columbus 94
Lawrence 94
Frankfurt am Main 93
São Paulo 92
Shanghai 86
North Charleston 85
Rome 84
Redwood City 83
Delft 81
New York 80
Dearborn 76
Kent 74
Helsinki 73
Medford 71
Turin 65
Chicago 62
Jakarta 62
Orem 58
Kenitra 56
Amsterdam 54
Dong Ket 54
Buffalo 51
Stockholm 49
Paris 47
Casablanca 44
Las Vegas 44
Guangzhou 42
Johannesburg 39
Da Nang 38
Manchester 38
San Diego 38
Montreal 37
Redmond 37
Brussels 36
Suwon 36
Istanbul 35
Nuremberg 35
Grenoble 34
Málaga 34
Rio de Janeiro 31
Warsaw 31
Belo Horizonte 30
Taipei 30
Haiphong 29
Zhengzhou 29
Brescia 28
Princeton 28
Chennai 27
Düsseldorf 27
Lappeenranta 25
Prague 25
Baghdad 24
Daejeon 24
Jacksonville 24
Phoenix 24
Shenzhen 24
Zurich 24
Ankara 23
Mumbai 23
Toronto 23
Abidjan 22
Alexandria 22
Basingstoke 22
Curitiba 22
Denver 22
Tashkent 22
Mexico City 21
Miami 21
Totale 14.377
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Nome #
Description of initial reference design and identification of safety aspects 350
Development of a control-oriented power plant simulator for the molten salt fast reactor 325
Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor 313
Development of best estimate numerical tools for LFR design and safety analysis 313
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project 295
Dynamics in natural circulation loop for internally heated molten salt 271
1D Modelica Modeling of the DYNASTY-eDYNASTY Coupled Natural Circulation Loops 258
OpenMC Analysis of TRIGA Mark II Reactor Void and Temperature Reactivity Coefficients 253
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants 244
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR 243
Development of an OpenFOAM multiphysics solver for solid fission products transport in the Molten Salt Fast Reactor 242
Dynamics of Natural Circulation in Presence of Distributed Heating: Results of the SAMOFAR CFD Simulation Campaign 241
Numerical methodology for design and evaluation of natural circulation systems for MSR applications 238
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor 238
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 238
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 234
Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation 233
Flow pattern visualization and definition of transition criteria for two-phase flow in Chevron-type corrugated channels 232
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response 230
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 226
Development of a control-oriented simulator for a LFR demonstrator 224
ALFRED reactor and hybrid systems: A test case 223
Dynamic Mode Decomposition for the Control of Nuclear Power Plants 218
Neutron Flux Reconstruction from Out-Core Sparse Measurements using Data-Driven Reduced Order Modelling 217
A CFD-based simulation tool for the stability analysis of natural circulation systems 217
Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor 217
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 215
A preliminary approach to the ALFRED reactor control strategy 203
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor 199
A Reduced Order Kalman Filter for Computational Fluid-Dynamics Applications 198
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches 198
A Serpent/OpenFOAM coupling approach for the study of the fuel burnup 196
1D modelling and preliminary analysis of the coupled DYNASTY–eDYNASTY natural circulation loop 195
A 3D CFD Model for the Study of Natural Circulation in the Pavia TRIGA Mark II Research Reactor 190
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts 190
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 186
Development of the ALFRED reactor full power mode control system 186
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events 186
Sub-channel thermal hydraulics analysis of the 250 kW TRIGA Mark II nuclear reactor 183
Instabilities of burnup calculations in a SERPENT/OPENFOAM coupling 183
Mass and Power Scaling of HALEU Fueled Heat-Pipe Nuclear Reactors for Selected Lunar Base scenarios 182
Advanced Modelling And Stability Analysis For Nuclear Reactors 182
Modeling and simulation of nuclear hybrid energy systems architectures 182
Analytical models for a small LFR core dynamics studies 180
Complete Thermal-Hydraulic Modelling of the Pavia TRIGA Mark II Research Reactor for the Study of the Natural Circulation Regime 180
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 180
A mass conservative Kalman filter algorithm for computational thermo-fluid dynamics 179
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor 179
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor 177
Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core 177
A coupled neutronic and thermal-hydraulic model for ALFRED 175
A multi-physics modelling approach for the analysis of Lead Fast Reactors 174
A New Reactivity Control Approach for Circulating Fuel Reactors 174
A comprehensive methodology for designing a nuclear electric propulsion (NEP) concept 171
Mass and Power Estimations of Moderated and Unmoderated HALEU Fueled Heat-Pipe Reactors for Space Applications 170
Modelling and CFD analysis of the DYNASTY loop facility 170
An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purposes 169
On the need for multi-dimensional models for the safety analysis of (fast-spectrum) Molten Salt Reactors 168
Dynamic modelling and optimisation of a Small Modular Reactor for electricity production and district heating in the Helsinki region 168
Multiphysics modelling of gaseous fission products in the Molten Salt Fast Reactor 167
ANALYSIS OF THE COOLANT DENSITY REACTIVITY COEFFICIENT IN LFRs AND SFRs VIA MONTE CARLO PERTURBATION/SENSITIVITY 165
Derivation and Implementation in OpenFOAM of a Point-Kinetics Model for Molten Salt Reactors 163
A multiphysics model for analysis of inert gas bubbles in Molten Salt Fast Reactor 162
Nuovo nucleare: Small Modular Reactors e sistemi energetici ibridi 161
A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset 161
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 2 : Application and Results 159
Reduced order modeling approach for parametrized thermal-hydraulics problems: inclusion of the energy equation in the POD-FV-ROM method 159
Petri-net based modelling approach for ALFRED reactor operation and control system design 158
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 1: Numerical Modelling 158
A Data-driven Incident Detection Method for the Safe Operation of Molten Salt Fast Reactors 157
Large Eddy Simulation of the Dynamic Behaviour of the Dynasty Natural Circulation Loop 157
Object-oriented modelling and simulation for the ALFRED dynamics 156
Improvement of the Control-Oriented Modelling of the GEN-IV Lead-Cooled Fast Reactor: Development of Reduced Order Methods 156
An Adjoint Proper Orthogonal Decomposition method for a neutronics reduced order model 156
Effects of a multi-physics coupling approach in Monte Carlo burnup calculations 155
Development of a Data-Driven Approach Based on Kalman Filtering for CFD Reactor Analysis 155
Multi-physics tools development 153
Multiphysics analysis of RANS-based turbulent transport of solid fission products in the Molten Salt Fast Reactor 153
Analysis of KRUSTY reactor behaviour with OFELIA environment 152
Stability analyses for the European LFR demonstrator 152
Evaluation of the Coolant Reactivity Coefficient Influence on the Dynamic Response of a Small LFR System 151
Adaptive simulation for failure identification in the Advanced Lead Fast Reactor European Demonstrator 150
A Serpent/OpenFOAM coupling for 3D burnup analysis 150
Linear Stability Analysis of a Heated Channel in the Supercritical Water Reactor 149
Non-intrusive system state reconstruction from indirect measurements: A novel approach based on Hybrid Data Assimilation methods 145
Development of best estimate numerical tools for LFR design and safety analysis 144
Modelling of the DYNASTY experimental facility for natural circulation under distributed heating 143
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 142
Preliminary results of the experimental campaign conducted on the DYNASTY natural circulation loop 141
IAEA INITIATIVE ON OPEN-SOURCE NUCLEAR CODES FOR REACTOR ANALYSIS 140
Hybrid data assimilation methods, Part I: Numerical comparison between GEIM and PBDW 138
Safety Issues Affecting the Feasibility of an Early High-Flux LFR Technology Demonstrator 138
An intrinsically safe facility for forefront research and training on nuclear technologies — Kinetics and dynamics 138
Hybrid Data Assimilation methods: application to the DYNASTY experimental facility 137
Preliminary validation of the 1D modeling of the DYNASTY natural circulation loop against results from water experimental campaign 136
Sensitivity And Uncertainty Analysis of the TRIGA Mark II Reactor Using First and Second Order Perturbation Theory 136
Preliminary analysis and design of the energy conversion system for the molten salt fast reactor 136
A reduced order model for fission gas diffusion in columnar grains 136
CFD Analysis of Air-Water Two-Phase Flow in a Helically Coiled Tube 134
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System 134
Totale 18.711
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Categoria #
all - tutte 67.143
article - articoli 34.782
book - libri 0
conference - conferenze 27.783
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 168
Totale 129.876
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021451 0 0 0 0 0 0 0 0 0 147 81 223
2021/2022875 61 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
2025/202612.355 1.977 1.947 748 1.076 795 680 1.955 944 991 1.242 0 0
Totale 25.223