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

LORENZI, STEFANO
 Distribuzione geografica
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Continente #
NA - Nord America 7.694
EU - Europa 6.389
AS - Asia 4.470
SA - Sud America 1.035
AF - Africa 326
OC - Oceania 13
Continente sconosciuto - Info sul continente non disponibili 2
AN - Antartide 1
Totale 19.930
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Nazione #
US - Stati Uniti d'America 7.388
RU - Federazione Russa 2.361
IT - Italia 1.840
SG - Singapore 1.531
CN - Cina 1.223
BR - Brasile 871
VN - Vietnam 399
GB - Regno Unito 347
KR - Corea 339
FR - Francia 328
DE - Germania 266
NL - Olanda 263
CA - Canada 208
AT - Austria 192
FI - Finlandia 150
JO - Giordania 122
IN - India 119
HK - Hong Kong 118
IE - Irlanda 117
MA - Marocco 112
ID - Indonesia 97
JP - Giappone 97
TR - Turchia 95
SE - Svezia 81
ES - Italia 77
UA - Ucraina 70
MX - Messico 63
CH - Svizzera 60
BE - Belgio 58
AR - Argentina 54
BD - Bangladesh 53
ZA - Sudafrica 53
EG - Egitto 47
IQ - Iraq 44
CZ - Repubblica Ceca 40
IR - Iran 35
PK - Pakistan 33
PL - Polonia 33
PH - Filippine 29
CO - Colombia 26
CI - Costa d'Avorio 25
DK - Danimarca 25
EC - Ecuador 24
DZ - Algeria 20
PY - Paraguay 18
SA - Arabia Saudita 17
UZ - Uzbekistan 17
RO - Romania 16
AE - Emirati Arabi Uniti 15
AU - Australia 13
CL - Cile 13
GR - Grecia 13
IL - Israele 13
NG - Nigeria 13
BJ - Benin 12
KE - Kenya 12
VE - Venezuela 12
LT - Lituania 11
SI - Slovenia 11
TW - Taiwan 11
BO - Bolivia 10
DO - Repubblica Dominicana 9
AZ - Azerbaigian 7
KG - Kirghizistan 7
KZ - Kazakistan 7
PE - Perù 7
CR - Costa Rica 6
MU - Mauritius 6
MY - Malesia 6
TH - Thailandia 6
TN - Tunisia 6
BG - Bulgaria 5
JM - Giamaica 5
LB - Libano 5
PT - Portogallo 5
TZ - Tanzania 5
ET - Etiopia 4
LI - Liechtenstein 4
OM - Oman 4
PS - Palestinian Territory 4
SN - Senegal 4
AM - Armenia 3
CY - Cipro 3
GH - Ghana 3
NI - Nicaragua 3
PA - Panama 3
BW - Botswana 2
GE - Georgia 2
HN - Honduras 2
HU - Ungheria 2
KH - Cambogia 2
LK - Sri Lanka 2
NO - Norvegia 2
SK - Slovacchia (Repubblica Slovacca) 2
TT - Trinidad e Tobago 2
A1 - Anonimo 1
AL - Albania 1
AQ - Antartide 1
BH - Bahrain 1
BY - Bielorussia 1
Totale 19.910
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Città #
Ashburn 1.226
Singapore 844
Santa Clara 708
Milan 678
Chandler 472
Fairfield 459
Moscow 374
Woodbridge 330
Hefei 309
Houston 255
Seattle 245
Wilmington 231
Vienna 181
Ann Arbor 167
Cambridge 165
Beijing 158
Council Bluffs 154
Los Angeles 152
Boardman 150
Amman 120
Dallas 113
Seoul 113
London 110
Dublin 109
Ottawa 106
Lawrence 94
Columbus 86
São Paulo 85
Ho Chi Minh City 83
Redwood City 83
Delft 81
Dearborn 76
Kent 74
San Jose 72
Medford 71
Hong Kong 69
New York 67
Tokyo 66
Frankfurt am Main 65
Rome 65
Helsinki 57
Shanghai 57
Turin 57
Kenitra 56
Chicago 55
Jakarta 55
Dong Ket 54
Hanoi 53
Amsterdam 49
Buffalo 47
Casablanca 43
Stockholm 40
Paris 37
Redmond 37
San Diego 37
Suwon 36
Brussels 35
Grenoble 34
Nuremberg 34
Montreal 33
Málaga 33
Johannesburg 32
Manchester 31
Belo Horizonte 30
Rio de Janeiro 29
Orem 28
Princeton 28
Zhengzhou 28
Brescia 27
Düsseldorf 27
Istanbul 25
Lappeenranta 25
The Dalles 25
Prague 24
Jacksonville 23
Phoenix 23
Abidjan 22
Alexandria 22
Ankara 22
Curitiba 21
Denver 21
Warsaw 21
Bologna 20
Miami 20
Zurich 20
Atlanta 19
Brooklyn 19
College Station 19
Fremont 19
Brasília 18
Gif-sur-yvette 18
Guangzhou 18
Oshawa 18
Pohang 18
Boston 17
Munich 17
Yongin-si 17
Changsha 16
Da Nang 16
Dhaka 16
Totale 10.864
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Nome #
Description of initial reference design and identification of safety aspects 313
Development of a control-oriented power plant simulator for the molten salt fast reactor 289
Development of best estimate numerical tools for LFR design and safety analysis 276
Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor 271
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project 249
Dynamics in natural circulation loop for internally heated molten salt 213
Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation 212
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 212
Development of a control-oriented simulator for a LFR demonstrator 209
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 209
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor 208
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR 204
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants 204
1D Modelica Modeling of the DYNASTY-eDYNASTY Coupled Natural Circulation Loops 202
OpenMC Analysis of TRIGA Mark II Reactor Void and Temperature Reactivity Coefficients 200
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response 200
Development of an OpenFOAM multiphysics solver for solid fission products transport in the Molten Salt Fast Reactor 193
Numerical methodology for design and evaluation of natural circulation systems for MSR applications 193
Dynamic Mode Decomposition for the Control of Nuclear Power Plants 193
Flow pattern visualization and definition of transition criteria for two-phase flow in Chevron-type corrugated channels 183
Dynamics of Natural Circulation in Presence of Distributed Heating: Results of the SAMOFAR CFD Simulation Campaign 182
Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor 182
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 179
A preliminary approach to the ALFRED reactor control strategy 177
A CFD-based simulation tool for the stability analysis of natural circulation systems 177
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor 176
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches 173
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events 172
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 168
Development of the ALFRED reactor full power mode control system 168
A Reduced Order Kalman Filter for Computational Fluid-Dynamics Applications 167
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts 167
ALFRED reactor and hybrid systems: A test case 166
Neutron Flux Reconstruction from Out-Core Sparse Measurements using Data-Driven Reduced Order Modelling 163
A Serpent/OpenFOAM coupling approach for the study of the fuel burnup 162
Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core 161
Analytical models for a small LFR core dynamics studies 159
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor 154
A 3D CFD Model for the Study of Natural Circulation in the Pavia TRIGA Mark II Research Reactor 154
Instabilities of burnup calculations in a SERPENT/OPENFOAM coupling 153
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor 152
Advanced Modelling And Stability Analysis For Nuclear Reactors 150
Complete Thermal-Hydraulic Modelling of the Pavia TRIGA Mark II Research Reactor for the Study of the Natural Circulation Regime 149
A mass conservative Kalman filter algorithm for computational thermo-fluid dynamics 148
A coupled neutronic and thermal-hydraulic model for ALFRED 146
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 146
Modelling and CFD analysis of the DYNASTY loop facility 145
1D modelling and preliminary analysis of the coupled DYNASTY–eDYNASTY natural circulation loop 141
Modeling and simulation of nuclear hybrid energy systems architectures 141
On the need for multi-dimensional models for the safety analysis of (fast-spectrum) Molten Salt Reactors 140
A multi-physics modelling approach for the analysis of Lead Fast Reactors 140
A multiphysics model for analysis of inert gas bubbles in Molten Salt Fast Reactor 138
An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purposes 138
A New Reactivity Control Approach for Circulating Fuel Reactors 138
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 137
Petri-net based modelling approach for ALFRED reactor operation and control system design 136
Mass and Power Estimations of Moderated and Unmoderated HALEU Fueled Heat-Pipe Reactors for Space Applications 135
Reduced order modeling approach for parametrized thermal-hydraulics problems: inclusion of the energy equation in the POD-FV-ROM method 135
Multiphysics modelling of gaseous fission products in the Molten Salt Fast Reactor 135
Stability analyses for the European LFR demonstrator 134
Sub-channel thermal hydraulics analysis of the 250 kW TRIGA Mark II nuclear reactor 133
An Adjoint Proper Orthogonal Decomposition method for a neutronics reduced order model 133
Evaluation of the Coolant Reactivity Coefficient Influence on the Dynamic Response of a Small LFR System 132
Object-oriented modelling and simulation for the ALFRED dynamics 132
Multi-physics tools development 132
Mass and Power Scaling of HALEU Fueled Heat-Pipe Nuclear Reactors for Selected Lunar Base scenarios 130
A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset 129
Large Eddy Simulation of the Dynamic Behaviour of the Dynasty Natural Circulation Loop 129
Adaptive simulation for failure identification in the Advanced Lead Fast Reactor European Demonstrator 129
Derivation and Implementation in OpenFOAM of a Point-Kinetics Model for Molten Salt Reactors 129
Dynamic modelling and optimisation of a Small Modular Reactor for electricity production and district heating in the Helsinki region 128
Linear Stability Analysis of a Heated Channel in the Supercritical Water Reactor 126
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 1: Numerical Modelling 126
Multiphysics analysis of RANS-based turbulent transport of solid fission products in the Molten Salt Fast Reactor 126
Development of a Data-Driven Approach Based on Kalman Filtering for CFD Reactor Analysis 125
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 124
Improvement of the Control-Oriented Modelling of the GEN-IV Lead-Cooled Fast Reactor: Development of Reduced Order Methods 124
A Data-driven Incident Detection Method for the Safe Operation of Molten Salt Fast Reactors 123
Effects of a multi-physics coupling approach in Monte Carlo burnup calculations 122
Safety Issues Affecting the Feasibility of an Early High-Flux LFR Technology Demonstrator 119
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 2 : Application and Results 119
ANALYSIS OF THE COOLANT DENSITY REACTIVITY COEFFICIENT IN LFRs AND SFRs VIA MONTE CARLO PERTURBATION/SENSITIVITY 118
A Serpent/OpenFOAM coupling for 3D burnup analysis 118
Development of best estimate numerical tools for LFR design and safety analysis 117
Modelling of the DYNASTY experimental facility for natural circulation under distributed heating 116
Preliminary results of the experimental campaign conducted on the DYNASTY natural circulation loop 116
A comprehensive methodology for designing a nuclear electric propulsion (NEP) concept 116
Hybrid Data Assimilation methods: application to the DYNASTY experimental facility 115
CFD Analysis of Air-Water Two-Phase Flow in a Helically Coiled Tube 114
Simplified 0-D semi-analytical model for fuel draining in molten salt reactors 114
Non-intrusive system state reconstruction from indirect measurements: A novel approach based on Hybrid Data Assimilation methods 113
An intrinsically safe facility for forefront research and training on nuclear technologies — Kinetics and dynamics 113
Preliminary analysis and design of the energy conversion system for the molten salt fast reactor 113
Analysis of KRUSTY reactor behaviour with OFELIA environment 112
Sensitivity And Uncertainty Analysis of the TRIGA Mark II Reactor Using First and Second Order Perturbation Theory 112
Nuovo nucleare: Small Modular Reactors e sistemi energetici ibridi 111
Hybrid data assimilation methods, Part I: Numerical comparison between GEIM and PBDW 111
Modeling Approaches for Dynamic Analyses of Innovative SMRs Compact Steam Generators 111
Multiphysics analysis of an in-core fission product removal system for the Molten Salt Fast Reactor 110
Impact of linear and non-linear kinetics models on a small LFR core dynamics 109
Totale 15.446
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Categoria #
all - tutte 59.470
article - articoli 31.050
book - libri 0
conference - conferenze 24.340
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 86
Totale 114.946
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021802 0 0 0 0 0 0 188 89 74 147 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
2025/20267.350 1.977 1.947 748 1.076 795 680 127 0 0 0 0 0
Totale 20.218