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

LORENZI, STEFANO
 Distribuzione geografica
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Continente #
NA - Nord America 4.318
EU - Europa 2.362
AS - Asia 882
AF - Africa 100
SA - Sud America 22
OC - Oceania 3
Continente sconosciuto - Info sul continente non disponibili 2
Totale 7.689
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Nazione #
US - Stati Uniti d'America 4.147
IT - Italia 1.191
CN - Cina 226
CA - Canada 165
VN - Vietnam 164
AT - Austria 156
GB - Regno Unito 156
FR - Francia 133
KR - Corea 125
NL - Olanda 125
JO - Giordania 117
DE - Germania 103
IE - Irlanda 86
FI - Finlandia 73
UA - Ucraina 56
ES - Italia 55
SE - Svezia 50
TR - Turchia 42
BE - Belgio 40
JP - Giappone 39
IN - India 38
EG - Egitto 37
CH - Svizzera 35
HK - Hong Kong 27
CZ - Repubblica Ceca 24
ID - Indonesia 23
IR - Iran 22
ZA - Sudafrica 21
SG - Singapore 17
RU - Federazione Russa 16
DK - Danimarca 13
PH - Filippine 12
RO - Romania 12
GR - Grecia 11
CO - Colombia 9
DZ - Algeria 9
NG - Nigeria 9
BR - Brasile 8
IL - Israele 8
SI - Slovenia 8
CI - Costa d'Avorio 6
MU - Mauritius 6
MX - Messico 6
MY - Malesia 5
TW - Taiwan 5
TZ - Tanzania 5
LT - Lituania 4
PL - Polonia 4
AR - Argentina 3
AU - Australia 3
MA - Marocco 3
TN - Tunisia 3
BG - Bulgaria 2
CL - Cile 2
KG - Kirghizistan 2
LI - Liechtenstein 2
LK - Sri Lanka 2
NO - Norvegia 2
PK - Pakistan 2
PS - Palestinian Territory 2
UZ - Uzbekistan 2
A1 - Anonimo 1
AM - Armenia 1
BD - Bangladesh 1
EE - Estonia 1
EU - Europa 1
GH - Ghana 1
HR - Croazia 1
MK - Macedonia 1
MT - Malta 1
PT - Portogallo 1
Totale 7.689
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Città #
Chandler 472
Fairfield 459
Milan 433
Woodbridge 330
Ashburn 311
Houston 249
Wilmington 231
Seattle 223
Ann Arbor 163
Cambridge 157
Vienna 154
Amman 115
Ottawa 106
Lawrence 93
Redwood City 83
Dublin 82
Dearborn 76
Delft 76
Medford 71
Beijing 62
Dong Ket 54
Rome 46
Helsinki 38
London 37
Redmond 37
San Diego 37
Málaga 33
Shanghai 32
Princeton 28
New York 26
Brussels 22
Los Angeles 22
Chicago 21
Jacksonville 21
Alexandria 20
Brescia 20
Fremont 19
Gif-sur-yvette 18
Hefei 18
Oshawa 18
Seoul 18
Tokyo 18
Pohang 17
Montreal 16
Norwalk 16
Zhengzhou 16
Bresso 15
Dallas 14
Miami 14
Paris 14
Torino 14
Bologna 13
Des Moines 13
Manchester 13
Prague 13
Bergamo 12
Madrid 12
Mountain View 12
Yongin-si 12
Zurich 12
Central 11
Geilenkirchen 11
Genova 11
Heusden-Zolder 11
Johannesburg 11
Los Alamos 11
Santa Rosa 11
Bengaluru 10
Daejeon 10
Grenoble 10
Urbana 10
Amsterdam 9
Boardman 9
Hope 9
Marseille 9
Stockholm 9
Vedano al Lambro 9
Washington 9
Bardolino 8
Berkeley 8
College Station 8
Como 8
Hangyang 8
Harderwijk 8
Provo 8
Turin 8
Cairo 7
Hong Kong 7
Istanbul 7
La Crescenta 7
Memmingen 7
Moscow 7
Raleigh 7
Southampton 7
Suwon 7
Varese 7
Aachen 6
Abidjan 6
Ankara 6
Atlanta 6
Totale 5.135
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Nome #
Description of initial reference design and identification of safety aspects 217
Development of a control-oriented power plant simulator for the molten salt fast reactor 185
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project 157
Development of a control-oriented simulator for a LFR demonstrator 145
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts 139
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor 131
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations 131
Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation 129
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants 128
Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor 126
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response 125
Development of the ALFRED reactor full power mode control system 113
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System 112
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor 109
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR 109
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor 105
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor 104
An Adjoint Proper Orthogonal Decomposition method for a neutronics reduced order model 102
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 101
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches 98
A CFD-based simulation tool for the stability analysis of natural circulation systems 98
Dynamic Mode Decomposition for the Control of Nuclear Power Plants 97
Evaluation of the Coolant Reactivity Coefficient Influence on the Dynamic Response of a Small LFR System 96
Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor 95
Complete Thermal-Hydraulic Modelling of the Pavia TRIGA Mark II Research Reactor for the Study of the Natural Circulation Regime 93
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor 92
Adaptive simulation for failure identification in the Advanced Lead Fast Reactor European Demonstrator 92
Analytical models for a small LFR core dynamics studies 91
A preliminary approach to the ALFRED reactor control strategy 86
Development of best estimate numerical tools for LFR design and safety analysis 85
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 82
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor 82
A Reduced Order Kalman Filter for Computational Fluid-Dynamics Applications 81
Reduced order modeling approach for parametrized thermal-hydraulics problems: inclusion of the energy equation in the POD-FV-ROM method 81
Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core 81
Development of an OpenFOAM multiphysics solver for solid fission products transport in the Molten Salt Fast Reactor 79
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events 79
Dynamics in natural circulation loop for internally heated molten salt 79
Petri-net based modelling approach for ALFRED reactor operation and control system design 78
Dynamics of Natural Circulation in Presence of Distributed Heating: Results of the SAMOFAR CFD Simulation Campaign 77
Instabilities of burnup calculations in a SERPENT/OPENFOAM coupling 77
Stability analyses for the European LFR demonstrator 75
A Serpent/OpenFOAM coupling approach for the study of the fuel burnup 74
An intrinsically safe facility for forefront research and training on nuclear technologies — Kinetics and dynamics 73
Object-oriented modelling and simulation for the ALFRED dynamics 72
A coupled neutronic and thermal-hydraulic model for ALFRED 72
Simplified 0-D semi-analytical model for fuel draining in molten salt reactors 71
A multiphysics model for analysis of inert gas bubbles in Molten Salt Fast Reactor 69
A reduced order model for investigating the dynamics of the Gen-IV LFR coolant pool 67
Definition and Selection of Transients 66
Development of a Data-Driven Approach Based on Kalman Filtering for CFD Reactor Analysis 66
A 3D CFD Model for the Study of Natural Circulation in the Pavia TRIGA Mark II Research Reactor 63
An analytical model for the study of a small LFR core dynamics: development and benchmark 62
Impact of linear and non-linear kinetics models on a small LFR core dynamics 61
Multi-physics tools development 61
A multi-physics modelling approach for the analysis of Lead Fast Reactors 61
Advanced Modelling And Stability Analysis For Nuclear Reactors 60
Improvement of the Control-Oriented Modelling of the GEN-IV Lead-Cooled Fast Reactor: Development of Reduced Order Methods 59
A mass conservative Kalman filter algorithm for computational thermo-fluid dynamics 59
Results from a multi-physics numerical benchmark for codes dedicated to molten salt fast reactors 58
POD-Galerkin reduced order methods for CFD using Finite Volume Discretisation: vortex shedding around a circular cylinder 57
Development of an Object-Oriented Dynamics Simulator for a LFR DEMO 57
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 1: Numerical Modelling 54
Safety Issues Affecting the Feasibility of an Early High-Flux LFR Technology Demonstrator 53
ANALYSIS OF THE COOLANT DENSITY REACTIVITY COEFFICIENT IN LFRs AND SFRs VIA MONTE CARLO PERTURBATION/SENSITIVITY 52
ALFRED reactor and hybrid systems: A test case 51
Preliminary analysis and design of the energy conversion system for the molten salt fast reactor 50
Coarse-mesh thermal-hydraulics and neutronics coupling for the ALFRED reactor 49
An Initiative for the Development and Application of Open-source Multi-physics Simulation in Support of R&D and E&T in Nuclear Science and Technology 49
An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purposes 49
A New Reactivity Control Approach for Circulating Fuel Reactors 49
Modeling Approaches for Dynamic Analyses of Innovative SMRs Compact Steam Generators 49
CFD Analysis of Air-Water Two-Phase Flow in a Helically Coiled Tube 48
A Serpent/OpenFOAM coupling for 3D burnup analysis 48
Multiphysics analysis of RANS-based turbulent transport of solid fission products in the Molten Salt Fast Reactor 48
Numerical methodology for design and evaluation of natural circulation systems for MSR applications 47
Study of a low-power, fast-neutron-based ADS 47
Reduced Order Methods for the Improvement of Control-Oriented Modelling of Nuclear Power Plants 47
Effects of a multi-physics coupling approach in Monte Carlo burnup calculations 47
Sensitivity And Uncertainty Analysis of the TRIGA Mark II Reactor Using First and Second Order Perturbation Theory 46
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 2 : Application and Results 44
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System 44
Multiphysics modelling of gaseous fission products in the Molten Salt Fast Reactor 43
Petri Net approach for a Lead-cooled Fast Reactor startup design 41
Development of best estimate numerical tools for LFR design and safety analysis 41
Modelling and CFD analysis of the DYNASTY loop facility 40
Linear Stability Analysis of a Heated Channel in the Supercritical Water Reactor 39
Definition of model-based control strategies for the Molten Salt Fast Reactor nuclear power plant 39
Verification and Validation studies 38
Void Coefficient Sensitivity Analysis for the Triga Mark II Reactor at L.E.N.A. (UniPV) 38
Sub-channel thermal hydraulics analysis of the 250 kW TRIGA Mark II nuclear reactor 37
Development of best estimate numerical tools for LFR design and safety analysis 37
Comparison of Several RANS Modelling for the Pavia TRIGA Mark II Research Reactor 36
Development of a reduced order model for fuel burnup analysis 35
Multiphysics analysis of an in-core fission product removal system for the Molten Salt Fast Reactor 34
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 34
Assessment of the integrated mass conservative Kalman filter algorithm for Computational Thermo-Fluid Dynamics on the TRIGA Mark II reactor 34
An empirical interpolation method for two-dimensional vector fields and vector measurements 33
Development of a power plant simulator 32
Modeling and Analysis of Nuclear Fuel Pin Behavior for Innovative Lead Cooled FBR 29
Totale 7.361
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Categoria #
all - tutte 24.973
article - articoli 13.972
book - libri 0
conference - conferenze 9.238
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 48.183
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2018/2019509 0 0 0 0 0 0 0 0 0 134 221 154
2019/20201.469 95 102 52 86 174 191 206 124 130 92 125 92
2020/20211.156 70 62 49 43 58 72 188 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
2023/20241.167 94 167 124 138 94 122 165 162 47 54 0 0
Totale 7.924