logo-polimi
Loading...
Manifesto
Struttura Corso di Studi
Cerca/Visualizza Manifesto
Regolamento didattico
Internazionalizzazione
Orario Personalizzato
Il tuo orario personalizzato è disabilitato
Abilita
Ricerche
Cerca Docenti
Attività docente
Cerca Insegnamenti
Cerca insegnamenti degli Ordinamenti precedenti al D.M.509
Erogati in lingua Inglese
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
DocenteCammi Antonio
QualificaProfessore associato a tempo pieno
Dipartimento d'afferenzaDipartimento di Energia
Settore Scientifico DisciplinareING-IND/19 - Impianti Nucleari
Curriculum VitaeScarica il CV (14.08Kb - 29/03/2018)
OrcIDhttps://orcid.org/0000-0003-1508-5935

Contatti
Orario di ricevimento
DipartimentoPianoUfficioGiornoOrarioTelefonoFaxNote
Ingegneria Nucleare, via Ponzio 34/3, Milano Leonardo----MartedìDalle 14:00
Alle 16:00
02.2399.6332--Si prega di fissare anticipatamente l'appuntamento.
E-mailantonio.cammi@polimi.it
Pagina web redatta a cura del docentehttp://www.energia.polimi.it/didattica/scheda_persona.php?id=64

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 >>)
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response (Mostra >>)
Impact of uncertainties on the safety performances of the LBE-XADS concept nuclear reactor (Mostra >>)
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects (Mostra >>)
A new approach for nuclear reactor analysis based on complex network theory (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 >>)
An Arbitrary Lagrangian Eulerian solver for shock imploding fissile materials (Mostra >>)
A coupled neutronics shock physics solver: implementation of an SN neutron transport module (Mostra >>)
Contributo in Atti di convegno
Safety Parameters Uncertainty and Sensitivity Analysis for High Flux Reactor at Institut Laue Langevin (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2018 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Articoli su riviste
Adaptive simulation for failure identification in the Advanced Lead Fast Reactor European Demonstrator (Mostra >>)
A non-equilibrium control oriented model for the pressurizer dynamics (Mostra >>)
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants (Mostra >>)
A mass conservative Kalman filter algorithm for computational thermo-fluid dynamics (Mostra >>)
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events (Mostra >>)
Monte Carlo integrated approach to radiological characterization for nuclear facilities decommissioning (Mostra >>)
MCNP model of L-54 M nuclear research reactor: development and preliminary verification (Mostra >>)
Stability analysis of the Supercritical Water Reactor by means of the root locus criterion (Mostra >>)
Contributo in Atti di convegno
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts (Mostra >>)
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor (Mostra >>)
Development of a Data-Driven Approach Based on Kalman Filtering for CFD Reactor Analysis (Mostra >>)
Effects of a multi-physics coupling approach in Monte Carlo burnup calculations (Mostra >>)
A multi-physics modelling approach for the analysis of Lead Fast Reactors (Mostra >>)
Dynamic Mode Decomposition for the Control of Nuclear Power Plants (Mostra >>)
Complete Thermal-Hydraulic Modelling of the Pavia TRIGA Mark II Research Reactor for the Study of the Natural Circulation Regime (Mostra >>)
Instabilities of burnup calculations in a SERPENT/OPENFOAM coupling (Mostra >>)
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 1: Numerical Modelling (Mostra >>)
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 2 : Application and Results (Mostra >>)
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project (Mostra >>)
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System (Mostra >>)
Application of the dynamic mode decomposition approach to the dispersion of radioactive contaminants in air (Mostra >>)
Abstract in Atti di convegno
A Reduced Order Kalman Filter for Computational Fluid-Dynamics Applications (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2017 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Articoli su riviste
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop (Mostra >>)
A reduced order model for investigating the dynamics of the Gen-IV LFR coolant pool (Mostra >>)
Stability analysis by means of information entropy: Assessment of a novel method against natural circulation experimental data (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 >>)
CFD Study of Two-phase Flow in a Helical Tube (Mostra >>)
A Serpent/OpenFOAM coupling approach for the study of the fuel burnup (Mostra >>)
Linear Stability Analysis of a Heated Channel in the Supercritical Water Reactor (Mostra >>)
A 3D CFD Model for the Study of Natural Circulation in the Pavia TRIGA Mark II Research Reactor (Mostra >>)
Comparison of Several RANS Modelling for the Pavia TRIGA Mark II Research Reactor (Mostra >>)
Linear Stability Analysis Of A Full Triga Reactor Plant In A Closed Loop (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 >>)
Neutrino physics with JUNO (Mostra >>)
Reduced Basis Approaches in Time-Dependent Non-Coercive Settings for Modelling the Movement of Nuclear Reactor Control Rods (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 >>)
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources (Mostra >>)
Fuel burnup analysis of the TRIGA Mark II reactor at the University of Pavia (Mostra >>)
Characterization of the TRIGA Mark II reactor full-power steady state (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 >>)
A Feasibility Study on In-Core Fuel Management via Quantum Particle Swarm Optimization (Mostra >>)
Object-Oriented Modeling and simulation of a TRIGA reactor plant with Dymola (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2015 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Articoli su riviste
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 >>)
A scheme of correlation for frictional pressure drop in steam-water two-phase flow in helicoidal tubes (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 >>)
CFD study of an air-water flow inside helically coiled pipes (Mostra >>)
Gas transfer model to design a ventilator for neonatal total liquid ventilation (Mostra >>)
Measurement and simulation of the neutron flux distribution in the TRIGA Mark II reactor core (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 >>)
manifesti v. 3.1.9 / 3.1.9
Area Servizi ICT
07/12/2019