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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
ProfessorCammi Antonio
QualificationAssociate professor
Belonging DepartmentDipartimento di Energia
Scientific-Disciplinary SectorING-IND/19 - Nuclear Power Plants
Curriculum VitaeDownload CV (14.08Kb - 29/03/2018)
OrcIDhttps://orcid.org/0000-0003-1508-5935

Contacts
Professor's office hours
DepartmentFloorOfficeDayTimetableTelephoneFaxNotes
Ingegneria Nucleare, via Ponzio 34/3, Milano Leonardo----TuesdayFrom 14:00
To 16:00
02.2399.6332--Si prega di fissare anticipatamente l'appuntamento.
E-mailantonio.cammi@polimi.it
Professor's personal websitehttp://www.energia.polimi.it/didattica/scheda_persona.php?id=64

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
Reduced order modeling approach for parametrized thermal-hydraulics problems: inclusion of the energy equation in the POD-FV-ROM method (Show >>)
Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor (Show >>)


List of publications and reserach products for the year 2019 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Journal Articles
Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor (Show >>)
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response (Show >>)
Impact of uncertainties on the safety performances of the LBE-XADS concept nuclear reactor (Show >>)
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects (Show >>)
A new approach for nuclear reactor analysis based on complex network theory (Show >>)
Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor (Show >>)
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches (Show >>)
An Arbitrary Lagrangian Eulerian solver for shock imploding fissile materials (Show >>)
A coupled neutronics shock physics solver: implementation of an SN neutron transport module (Show >>)
Development of a control-oriented power plant simulator for the molten salt fast reactor (Show >>)
Simplified 0-D semi-analytical model for fuel draining in molten salt reactors (Show >>)
A CFD-based simulation tool for the stability analysis of natural circulation systems (Show >>)
Conference proceedings
Safety Parameters Uncertainty and Sensitivity Analysis for High Flux Reactor at Institut Laue Langevin (Show >>)
Sensitivity And Uncertainty Analysis of the TRIGA Mark II Reactor Using First and Second Order Perturbation Theory (Show >>)
Poster
A 3D MULTI-PHYSICS MODELLING OF THE TRIGA MARK II REACTOR (Show >>)


List of publications and reserach products for the year 2018 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Journal Articles
Adaptive simulation for failure identification in the Advanced Lead Fast Reactor European Demonstrator (Show >>)
A non-equilibrium control oriented model for the pressurizer dynamics (Show >>)
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants (Show >>)
The application of nodal method for dynamic analysis of TRIGA Mark II (Show >>)
Stability analysis of the Generation-IV nuclear reactors by means of the root locus criterion (Show >>)
Setting-up a control-oriented model for simulation of TRIGA Mark II dynamic response (Show >>)
A new model with Serpent for the first criticality benchmarks of the TRIGA Mark II reactor (Show >>)
A mass conservative Kalman filter algorithm for computational thermo-fluid dynamics (Show >>)
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events (Show >>)
Monte Carlo integrated approach to radiological characterization for nuclear facilities decommissioning (Show >>)
MCNP model of L-54 M nuclear research reactor: development and preliminary verification (Show >>)
Stability analysis of the Supercritical Water Reactor by means of the root locus criterion (Show >>)
Conference proceedings
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts (Show >>)
Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor (Show >>)
Development of a Data-Driven Approach Based on Kalman Filtering for CFD Reactor Analysis (Show >>)
Effects of a multi-physics coupling approach in Monte Carlo burnup calculations (Show >>)
A multi-physics modelling approach for the analysis of Lead Fast Reactors (Show >>)
Dynamic Mode Decomposition for the Control of Nuclear Power Plants (Show >>)
Complete Thermal-Hydraulic Modelling of the Pavia TRIGA Mark II Research Reactor for the Study of the Natural Circulation Regime (Show >>)
Instabilities of burnup calculations in a SERPENT/OPENFOAM coupling (Show >>)
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 1: Numerical Modelling (Show >>)
A Multiphysics Model for Analysis of Inert Gas Bubbles in Molten Salt Fast Reactor – Part 2 : Application and Results (Show >>)
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project (Show >>)
Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System (Show >>)
Application of the dynamic mode decomposition approach to the dispersion of radioactive contaminants in air (Show >>)
Abstract in Atti di convegno
A Reduced Order Kalman Filter for Computational Fluid-Dynamics Applications (Show >>)


List of publications and reserach products for the year 2017 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Journal Articles
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop (Show >>)
A reduced order model for investigating the dynamics of the Gen-IV LFR coolant pool (Show >>)
Stability analysis by means of information entropy: Assessment of a novel method against natural circulation experimental data (Show >>)
Contributions on scientific books
Thermal hydraulics of liquid-fueled MSRs (Show >>)
Conference proceedings
Reduced Order Methods for the Improvement of Control-Oriented Modelling of Nuclear Power Plants (Show >>)
An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR (Show >>)
CFD Study of Two-phase Flow in a Helical Tube (Show >>)
A Serpent/OpenFOAM coupling approach for the study of the fuel burnup (Show >>)
Linear Stability Analysis of a Heated Channel in the Supercritical Water Reactor (Show >>)
A 3D CFD Model for the Study of Natural Circulation in the Pavia TRIGA Mark II Research Reactor (Show >>)
Comparison of Several RANS Modelling for the Pavia TRIGA Mark II Research Reactor (Show >>)
Linear Stability Analysis Of A Full Triga Reactor Plant In A Closed Loop (Show >>)


List of publications and reserach products for the year 2016 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Journal Articles
A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel (Show >>)
Petri-net based modelling approach for ALFRED reactor operation and control system design (Show >>)
Analytical and numerical investigation of the heat exchange effect on the dynamic behaviour of natural circulation with internally heated fluids (Show >>)
A Reduced Basis Approach for Modelling the Movement of Nuclear Reactor Control Rods (Show >>)
Neutrino physics with JUNO (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 >>)
POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations (Show >>)
An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources (Show >>)
Fuel burnup analysis of the TRIGA Mark II reactor at the University of Pavia (Show >>)
Characterization of the TRIGA Mark II reactor full-power steady state (Show >>)
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 >>)
A Feasibility Study on In-Core Fuel Management via Quantum Particle Swarm Optimization (Show >>)
Object-Oriented Modeling and simulation of a TRIGA reactor plant with Dymola (Show >>)
manifesti v. 3.2.0 / 3.2.0
Area Servizi ICT
29/01/2020