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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 2022 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Journal Articles
Development and implementation of a multi-physics high fidelity model of the TRIGA mark II reactor (Show >>)
Multiphysics analysis of RANS-based turbulent transport of solid fission products in the Molten Salt Fast Reactor (Show >>)
Multiphysics modelling of gaseous fission products in the Molten Salt Fast Reactor (Show >>)


List of publications and reserach products for the year 2021 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Conference proceedings
A New Reactivity Control Approach for Circulating Fuel Reactors (Show >>)
Adoption of ACPS in Nuclear Reactor Analysis (Show >>)
Advanced Modelling And Stability Analysis For Nuclear Reactors (Show >>)
Dynamic Response of LFR in Cogeneration Mode (Show >>)
First numerical evaluation of the thermal performance of a tubular receiver equipped with raschig rings for csp applications (Show >>)
Implementing Large-Scale Hybrid Desalination System Driven by Alfred Reactor and Parabolic-Trough Solar Power Plant, Equipped with Phase Change Material Storage System: The Case of Emirate (Show >>)
Multiphysics Topology Optimization with Application to Molten Salt Fast Reactor (Show >>)
Non-Modal Stability Analysis of the Zero-Dimensional Model of the TRIGA Mark II Reactor (Show >>)
Journal Articles
A new lumped approach for the simulation of the magnetron injection gun for megawatt-class eu gyrotrons (Show >>)
An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purposes (Show >>)
An empirical interpolation method for two-dimensional vector fields and vector measurements (Show >>)
Application of adjoint-based sensitivity analysis to natural circulation of high-Pr fluid inside heat transport system (Show >>)
Assessment of the integrated mass conservative Kalman filter algorithm for Computational Thermo-Fluid Dynamics on the TRIGA Mark II reactor (Show >>)
Calculation of gamma-ray exposure buildup factor based on backpropagation neural network (Show >>)
Calibration strategy of the JUNO experiment (Show >>)
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System (Show >>)
Definition of model-based control strategies for the Molten Salt Fast Reactor nuclear power plant (Show >>)
Development of a CFD – LES model for the dynamic analysis of the DYNASTY natural circulation loop (Show >>)
Embedded readout electronics R&D for the large PMTs in the JUNO experiment (Show >>)
Experimental and numerical results of LIFUS5/Mod3 series E test on in-box LOCA transient for WCLL-BB (Show >>)
FPGA Implementation of an NCO Based CDR for the JUNO Front-End Electronics (Show >>)
Feasibility and physics potential of detecting 8B solar neutrinos at JUNO (Show >>)
Improving the overall thermal performance of parabolic trough solar collectors using porous media (Show >>)
JUNO sensitivity to low energy atmospheric neutrino spectra (Show >>)
Optimization of the JUNO liquid scintillator composition using a Daya Bay antineutrino detector (Show >>)
Radioactivity control strategy for the JUNO detector (Show >>)
Reduced order modeling for coupled thermal-hydraulics and reactor physics problems (Show >>)
The design and sensitivity of JUNO’s scintillator radiopurity pre-detector OSIRIS (Show >>)


List of publications and reserach products for the year 2020 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Conference proceedings
Large-Eddy simulation of the TRIGA Mark II Reactor Core (Show >>)
Requirements of LES in Modelling Natural Circulation Loops: Preliminary Study in a Pipe Geometry (Show >>)
Void Coefficient Sensitivity Analysis for the Triga Mark II Reactor at L.E.N.A. (UniPV) (Show >>)
Journal Articles
A Kalman Filter-Based Approach for Online Source-Term Estimation in Accidental Radioactive Dispersion Events (Show >>)
A Serpent/OpenFOAM coupling for 3D burnup analysis (Show >>)
A coupled neutronic and thermal-hydraulic model for ALFRED (Show >>)
A multiphysics model for analysis of inert gas bubbles in Molten Salt Fast Reactor (Show >>)
Adjoint‐based sensitivity analysis of circulating liquid fuel system for the multiphysics model of molten salt reactor (Show >>)
An Arbitrary Lagrangian-Eulerian, coupled neutronics-shock physics model for the analysis of shockwave implosion of solid fissile materials (Show >>)
Development of a reduced order model for fuel burnup analysis (Show >>)
Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core (Show >>)
Lattice boltzmann method applied to nuclear reactors-A systematic literature review (Show >>)
Preliminary analysis and design of the energy conversion system for the molten salt fast reactor (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 >>)
Stability analysis of a zero-dimensional model of PWR core using non-modal stability theory (Show >>)
Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility (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 >>)
manifesti v. 3.4.25 / 3.4.25
Area Servizi ICT
27/06/2022