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Le informazioni sulla didattica, sulla ricerca e sui compiti istituzionali riportate in questa pagina sono certificate dall'Ateneo; ulteriori informazioni, redatte a cura del docente, sono disponibili sulla pagina web personale e nel curriculum vitae indicati nella scheda.
Informazioni sul docente
DocenteLuzzi Lelio
QualificaProfessore associato a tempo pieno
Dipartimento d'afferenzaDipartimento di Energia
Settore Scientifico DisciplinareING-IND/19 - Impianti Nucleari
Curriculum VitaeScarica il CV (20.89Kb - 14/09/2017)
OrcIDhttps://orcid.org/0000-0002-9754-4535

Contatti
Orario di ricevimento
DipartimentoPianoUfficioGiornoOrarioTelefonoFaxNote
Energia (Sezione di Ingegneria Nucleare)------Dalle 10:
Alle 18:
6326--Ricevimento in Bovisa (Edificio 12, I piano, via La Masa 34), previo appuntamento via mail.
E-maillelio.luzzi@polimi.it
Pagina web redatta a cura del docentehttp://www.energia.polimi.it/english/department/scheda_persona.php?id=89

Fonte dati: RE.PUBLIC@POLIMI - Research Publications at Politecnico di Milano

Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2019 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Articoli su riviste
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor (Mostra >>)
Isotropic softening model for fuel cracking in BISON (Mostra >>)
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects (Mostra >>)
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor (Mostra >>)
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2018 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Articoli su riviste
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations (Mostra >>)
Synthesis of plutonium trifluoride by hydro-fluorination and novel thermodynamic data for the PuF3-LiF system (Mostra >>)
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools (Mostra >>)
DarkSide-20k: A 20 tonne two-phase LAr TPC for direct dark matter detection at LNGS (Mostra >>)
Vaporization behaviour of the Molten Salt Fast Reactor fuel: The LiF-ThF4-UF4 system (Mostra >>)
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution (Mostra >>)
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant (Mostra >>)
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events (Mostra >>)
Contributo in Atti di convegno
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor (Mostra >>)
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis (Mostra >>)
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System (Mostra >>)
Modelling and Assessment of Inert Gas Behaviour in UO2 Nuclear Fuel for Transient Analysis (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2017 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Articoli su riviste
Spark plasma sintering of fine uranium carbide powder (Mostra >>)
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop (Mostra >>)
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS (Mostra >>)
A reduced order model for investigating the dynamics of the Gen-IV LFR coolant pool (Mostra >>)
A semi-empirical model for the formation and depletion of the high burnup structure in UO2 (Mostra >>)
Stability analysis by means of information entropy: Assessment of a novel method against natural circulation experimental data (Mostra >>)
The DarkSide experiment (Mostra >>)
Cryogenic Characterization of FBK RGB-HD SiPMs (Mostra >>)
Contributi su volumi (Capitolo o Saggio)
Thermal hydraulics of liquid-fueled MSRs (Mostra >>)
Contributo in Atti di convegno
Reduced Order Methods for the Improvement of Control-Oriented Modelling of Nuclear Power Plants (Mostra >>)
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR (Mostra >>)
Modelling Fission Gas Behaviour with the BISON Fuel Performance Code (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2016 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Articoli su riviste
A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel (Mostra >>)
Petri-net based modelling approach for ALFRED reactor operation and control system design (Mostra >>)
Analytical and numerical investigation of the heat exchange effect on the dynamic behaviour of natural circulation with internally heated fluids (Mostra >>)
A Reduced Basis Approach for Modelling the Movement of Nuclear Reactor Control Rods (Mostra >>)
Reduced Basis Approaches in Time-Dependent Non-Coercive Settings for Modelling the Movement of Nuclear Reactor Control Rods (Mostra >>)
PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release (Mostra >>)
Microhardness and Young's modulus of high burn-up UO2 fuel (Mostra >>)
The influence of the wall thermal inertia over a single-phase natural convection loop with internally heated fluids (Mostra >>)
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations (Mostra >>)
Innovative preparation route for uranium carbide using citric acid as a carbon source (Mostra >>)
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources (Mostra >>)
Contributo in Atti di convegno
DYNASTY: An Experimental Loop for the Study of Natural Circulation with Internally Heated Fluids (Mostra >>)
Improvement of the Control-Oriented Modelling of the GEN-IV Lead-Cooled Fast Reactor: Development of Reduced Order Methods (Mostra >>)
The Role of Italian universities/CIRTEN for the engineering study of a fission-fusion hybrid reactor (FFHR) (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2015 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Articoli su riviste
Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling (Mostra >>)
A laser heating study of the CeO2 solid/liquid transition: challenges related to a refractory compound with a very high oxygen pressure (Mostra >>)
Dynamic stability of natural circulation loops for single phase fluids with internal heat generation (Mostra >>)
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics (Mostra >>)
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor (Mostra >>)
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor (Mostra >>)
Development of the ALFRED reactor full power mode control system (Mostra >>)
Contributo in Atti di convegno
Spatial neutronics modelling to evaluate the temperature reactivity feedbacks in a Lead-cooled Fast Reactor (Mostra >>)
Extension of the FAST code system for the modelling and simulation of MSR dynamics (Mostra >>)
Reduced Order Methods: Applications to Nuclear Reactor Core Spatial Dynamics (Mostra >>)
Modeling and Assessment of PCI in LWR Fuel (Mostra >>)
Modelling of Burst Release in Oxide Fuel and Application to the Transuranus Code (Mostra >>)
manifesti v. 3.1.9 / 3.1.9
Area Servizi ICT
13/12/2019