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Information on didactic, research and institutional assignments on this page are certified by the University; more information, prepared by the professor, are available on the personal web page and in the curriculum vitae indicated on this webpage.
Information on professor
ProfessorLuzzi Lelio
QualificationAssociate professor full time
Belonging DepartmentDipartimento di Energia
Scientific-Disciplinary SectorING-IND/19 - Nuclear Power Plants
Curriculum VitaeDownload CV (20.89Kb - 14/09/2017)
OrcIDhttps://orcid.org/0000-0002-9754-4535

Contacts
Professor's office hours
DepartmentFloorOfficeDayTimetableTelephoneFaxNotes
Energia (Sezione di Ingegneria Nucleare)------From 10:
To 18:
6326--To make an appointment, please write an e-mail to: lelio.luzzi@polimi.it
E-maillelio.luzzi@polimi.it
Professor's personal websitehttp://www.energia.polimi.it/english/department/scheda_persona.php?id=89

Data source: RE.PUBLIC@POLIMI - Research Publications at Politecnico di Milano

List of publications and reserach products for the year 2020 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Journal Articles
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes (Show >>)


List of publications and reserach products for the year 2019 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Conference proceedings
Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions (Show >>)
The Application of the TRANSURANUS Fuel Performance Code to WWER Fuel: An Overview (Show >>)
Journal Articles
A CFD-based simulation tool for the stability analysis of natural circulation systems (Show >>)
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor (Show >>)
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor (Show >>)
Fuel Modelling in Accident Conditions (FUMAC) (Show >>)
Isobaric heat capacity of solid and liquid thorium tetrafluoride (Show >>)
Isotropic softening model for fuel cracking in BISON (Show >>)
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches (Show >>)
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions (Show >>)
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects (Show >>)
Vaporization behaviour of a PuF3-containing fuel mixture for the Molten Salt Fast Reactor (Show >>)


List of publications and reserach products for the year 2018 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Conference proceedings
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor (Show >>)
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System (Show >>)
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis (Show >>)
Modelling and Assessment of Inert Gas Behaviour in UO2 Nuclear Fuel for Transient Analysis (Show >>)
Journal Articles
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools (Show >>)
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events (Show >>)
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution (Show >>)
DarkSide-20k: A 20 tonne two-phase LAr TPC for direct dark matter detection at LNGS (Show >>)
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations (Show >>)
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant (Show >>)
Synthesis of plutonium trifluoride by hydro-fluorination and novel thermodynamic data for the PuF3-LiF system (Show >>)
Vaporization behaviour of the Molten Salt Fast Reactor fuel: The LiF-ThF4-UF4 system (Show >>)


List of publications and reserach products for the year 2017 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Contributions on scientific books
Thermal hydraulics of liquid-fueled MSRs (Show >>)
Conference proceedings
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR (Show >>)
Modelling Fission Gas Behaviour with the BISON Fuel Performance Code (Show >>)
Reduced Order Methods for the Improvement of Control-Oriented Modelling of Nuclear Power Plants (Show >>)
Journal Articles
A reduced order model for investigating the dynamics of the Gen-IV LFR coolant pool (Show >>)
A semi-empirical model for the formation and depletion of the high burnup structure in UO2 (Show >>)
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS (Show >>)
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop (Show >>)
Cryogenic Characterization of FBK RGB-HD SiPMs (Show >>)
Spark plasma sintering of fine uranium carbide powder (Show >>)
Stability analysis by means of information entropy: Assessment of a novel method against natural circulation experimental data (Show >>)
The DarkSide experiment (Show >>)


List of publications and reserach products for the year 2016 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Conference proceedings
DYNASTY: An Experimental Loop for the Study of Natural Circulation with Internally Heated Fluids (Show >>)
Improvement of the Control-Oriented Modelling of the GEN-IV Lead-Cooled Fast Reactor: Development of Reduced Order Methods (Show >>)
The Role of Italian universities/CIRTEN for the engineering study of a fission-fusion hybrid reactor (FFHR) (Show >>)
Journal Articles
A Reduced Basis Approach for Modelling the Movement of Nuclear Reactor Control Rods (Show >>)
A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel (Show >>)
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources (Show >>)
Analytical and numerical investigation of the heat exchange effect on the dynamic behaviour of natural circulation with internally heated fluids (Show >>)
Innovative preparation route for uranium carbide using citric acid as a carbon source (Show >>)
Microhardness and Young's modulus of high burn-up UO2 fuel (Show >>)
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations (Show >>)
Petri-net based modelling approach for ALFRED reactor operation and control system design (Show >>)
PolyPole-1: An accurate numerical algorithm for intra-granular fission gas release (Show >>)
Reduced Basis Approaches in Time-Dependent Non-Coercive Settings for Modelling the Movement of Nuclear Reactor Control Rods (Show >>)
The influence of the wall thermal inertia over a single-phase natural convection loop with internally heated fluids (Show >>)
manifesti v. 3.4.6 / 3.4.6
Area Servizi ICT
24/11/2020