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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 full time
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
An Arbitrary Lagrangian-Eulerian, coupled neutronics-shock physics model for the analysis of shockwave implosion of solid fissile materials (Show >>)
Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor (Show >>)
Reduced order modeling approach for parametrized thermal-hydraulics problems: inclusion of the energy equation in the POD-FV-ROM method (Show >>)


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


List of publications and reserach products for the year 2018 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Abstract in Atti di convegno
A Reduced Order Kalman Filter for Computational Fluid-Dynamics Applications (Show >>)
Conference proceedings
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 >>)
A multi-physics modelling approach for the analysis of Lead Fast Reactors (Show >>)
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 >>)
Application of the dynamic mode decomposition approach to the dispersion of radioactive contaminants in air (Show >>)
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts (Show >>)
Complete Thermal-Hydraulic Modelling of the Pavia TRIGA Mark II Research Reactor for the Study of the Natural Circulation Regime (Show >>)
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project (Show >>)
Development of a Data-Driven Approach Based on Kalman Filtering for CFD Reactor Analysis (Show >>)
Dynamic Mode Decomposition for the Control of Nuclear Power Plants (Show >>)
Effects of a multi-physics coupling approach in Monte Carlo burnup calculations (Show >>)
Instabilities of burnup calculations in a SERPENT/OPENFOAM coupling (Show >>)
Journal Articles
A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants (Show >>)
A mass conservative Kalman filter algorithm for computational thermo-fluid dynamics (Show >>)
A new model with Serpent for the first criticality benchmarks of the TRIGA Mark II reactor (Show >>)
A non-equilibrium control oriented model for the pressurizer dynamics (Show >>)
Adaptive simulation for failure identification in the Advanced Lead Fast Reactor European Demonstrator (Show >>)
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events (Show >>)
MCNP model of L-54 M nuclear research reactor: development and preliminary verification (Show >>)
Monte Carlo integrated approach to radiological characterization for nuclear facilities decommissioning (Show >>)
Setting-up a control-oriented model for simulation of TRIGA Mark II dynamic response (Show >>)
Stability analysis of the Generation-IV nuclear reactors by means of the root locus criterion (Show >>)
Stability analysis of the Supercritical Water Reactor by means of the root locus criterion (Show >>)
The application of nodal method for dynamic analysis of TRIGA Mark II (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
A 3D CFD Model for the Study of Natural Circulation in the Pavia TRIGA Mark II Research Reactor (Show >>)
A Serpent/OpenFOAM coupling approach for the study of the fuel burnup (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 >>)
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 >>)
Linear Stability Analysis of a Heated Channel in the Supercritical Water Reactor (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 >>)
Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop (Show >>)
Stability analysis by means of information entropy: Assessment of a novel method against natural circulation experimental data (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
A Feasibility Study on In-Core Fuel Management via Quantum Particle Swarm Optimization (Show >>)
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 >>)
Object-Oriented Modeling and simulation of a TRIGA reactor plant with Dymola (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 >>)
Characterization of the TRIGA Mark II reactor full-power steady state (Show >>)
Fuel burnup analysis of the TRIGA Mark II reactor at the University of Pavia (Show >>)
Neutrino physics with JUNO (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 >>)
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. 3.3.7 / 3.3.7
Area Servizi ICT
12/07/2020