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


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2021 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Contributi su volumi (Capitolo o Saggio)
The TRANSURANUS fuel performance code (Mostra >>)
Contributo in Atti di convegno
A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes (Mostra >>)
Articoli su riviste
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors (Mostra >>)
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment (Mostra >>)
Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON (Mostra >>)
Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data (Mostra >>)
SiPM-matrix readout of two-phase argon detectors using electroluminescence in the visible and near infrared range (Mostra >>)
Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel (Mostra >>)
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2020 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Articoli su riviste
Design and construction of a new detector to measure ultra-low radioactive-isotope contamination of argon (Mostra >>)
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation (Mostra >>)
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients (Mostra >>)
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications (Mostra >>)
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2019 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Contributo in Atti di convegno
DarkSide-50 results and the future liquid argon dark matter program (Mostra >>)
Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions (Mostra >>)
The Application of the TRANSURANUS Fuel Performance Code to WWER Fuel: An Overview (Mostra >>)
Articoli su riviste
A CFD-based simulation tool for the stability analysis of natural circulation systems (Mostra >>)
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor (Mostra >>)
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor (Mostra >>)
Fuel Modelling in Accident Conditions (FUMAC) (Mostra >>)
Isobaric heat capacity of solid and liquid thorium tetrafluoride (Mostra >>)
Isotropic softening model for fuel cracking in BISON (Mostra >>)
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches (Mostra >>)
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions (Mostra >>)
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects (Mostra >>)
Vaporization behaviour of a PuF3-containing fuel mixture for the Molten Salt Fast Reactor (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2018 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Contributo in Atti di convegno
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor (Mostra >>)
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System (Mostra >>)
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis (Mostra >>)
Modelling and Assessment of Inert Gas Behaviour in UO2 Nuclear Fuel for Transient Analysis (Mostra >>)
Articoli su riviste
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools (Mostra >>)
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events (Mostra >>)
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution (Mostra >>)
DarkSide-20k: A 20 tonne two-phase LAr TPC for direct dark matter detection at LNGS (Mostra >>)
Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations (Mostra >>)
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant (Mostra >>)
Synthesis of plutonium trifluoride by hydro-fluorination and novel thermodynamic data for the PuF3-LiF system (Mostra >>)
Vaporization behaviour of the Molten Salt Fast Reactor fuel: The LiF-ThF4-UF4 system (Mostra >>)
manifesti v. 3.5.1 / 3.5.1
Area Servizi ICT
27/11/2022