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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 (120.23Kb - 06/03/2021)
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 2022 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Journal Articles
Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions (Show >>)
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor (Show >>)
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution (Show >>)
On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation (Show >>)
On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error (Show >>)
Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX (Show >>)
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX (Show >>)


List of publications and reserach products for the year 2021 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Contributions on scientific books
The TRANSURANUS fuel performance code (Show >>)
Conference proceedings
A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes (Show >>)
Journal Articles
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors (Show >>)
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment (Show >>)
Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON (Show >>)
Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data (Show >>)
SiPM-matrix readout of two-phase argon detectors using electroluminescence in the visible and near infrared range (Show >>)
Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel (Show >>)
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes (Show >>)


List of publications and reserach products for the year 2020 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Journal Articles
Design and construction of a new detector to measure ultra-low radioactive-isotope contamination of argon (Show >>)
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation (Show >>)
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients (Show >>)
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications (Show >>)
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
DarkSide-50 results and the future liquid argon dark matter program (Show >>)
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 >>)
manifesti v. 3.5.1 / 3.5.1
Area Servizi ICT
02/12/2022