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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
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 2022 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Articoli su riviste
Development and implementation of a multi-physics high fidelity model of the TRIGA mark II reactor (Mostra >>)
Multiphysics analysis of RANS-based turbulent transport of solid fission products in the Molten Salt Fast Reactor (Mostra >>)
Multiphysics modelling of gaseous fission products in the Molten Salt Fast Reactor (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2021 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Contributo in Atti di convegno
A New Reactivity Control Approach for Circulating Fuel Reactors (Mostra >>)
Adoption of ACPS in Nuclear Reactor Analysis (Mostra >>)
Advanced Modelling And Stability Analysis For Nuclear Reactors (Mostra >>)
Dynamic Response of LFR in Cogeneration Mode (Mostra >>)
First numerical evaluation of the thermal performance of a tubular receiver equipped with raschig rings for csp applications (Mostra >>)
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 (Mostra >>)
Multiphysics Topology Optimization with Application to Molten Salt Fast Reactor (Mostra >>)
Non-Modal Stability Analysis of the Zero-Dimensional Model of the TRIGA Mark II Reactor (Mostra >>)
Articoli su riviste
A new lumped approach for the simulation of the magnetron injection gun for megawatt-class eu gyrotrons (Mostra >>)
An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purposes (Mostra >>)
An empirical interpolation method for two-dimensional vector fields and vector measurements (Mostra >>)
Application of adjoint-based sensitivity analysis to natural circulation of high-Pr fluid inside heat transport system (Mostra >>)
Assessment of the integrated mass conservative Kalman filter algorithm for Computational Thermo-Fluid Dynamics on the TRIGA Mark II reactor (Mostra >>)
Calculation of gamma-ray exposure buildup factor based on backpropagation neural network (Mostra >>)
Calibration strategy of the JUNO experiment (Mostra >>)
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System (Mostra >>)
Definition of model-based control strategies for the Molten Salt Fast Reactor nuclear power plant (Mostra >>)
Derivation and Implementation in OpenFOAM of a Point-Kinetics Model for Molten Salt Reactors (Mostra >>)
Development of a CFD – LES model for the dynamic analysis of the DYNASTY natural circulation loop (Mostra >>)
Embedded readout electronics R&D for the large PMTs in the JUNO experiment (Mostra >>)
Experimental and numerical results of LIFUS5/Mod3 series E test on in-box LOCA transient for WCLL-BB (Mostra >>)
FPGA Implementation of an NCO Based CDR for the JUNO Front-End Electronics (Mostra >>)
Feasibility and physics potential of detecting 8B solar neutrinos at JUNO (Mostra >>)
Improving the overall thermal performance of parabolic trough solar collectors using porous media (Mostra >>)
JUNO sensitivity to low energy atmospheric neutrino spectra (Mostra >>)
Optimization of the JUNO liquid scintillator composition using a Daya Bay antineutrino detector (Mostra >>)
Radioactivity control strategy for the JUNO detector (Mostra >>)
Reduced order modeling for coupled thermal-hydraulics and reactor physics problems (Mostra >>)
The design and sensitivity of JUNO’s scintillator radiopurity pre-detector OSIRIS (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2020 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Contributo in Atti di convegno
Large-Eddy simulation of the TRIGA Mark II Reactor Core (Mostra >>)
Requirements of LES in Modelling Natural Circulation Loops: Preliminary Study in a Pipe Geometry (Mostra >>)
Void Coefficient Sensitivity Analysis for the Triga Mark II Reactor at L.E.N.A. (UniPV) (Mostra >>)
Articoli su riviste
A Kalman Filter-Based Approach for Online Source-Term Estimation in Accidental Radioactive Dispersion Events (Mostra >>)
A Serpent/OpenFOAM coupling for 3D burnup analysis (Mostra >>)
A coupled neutronic and thermal-hydraulic model for ALFRED (Mostra >>)
A multiphysics model for analysis of inert gas bubbles in Molten Salt Fast Reactor (Mostra >>)
Adjoint‐based sensitivity analysis of circulating liquid fuel system for the multiphysics model of molten salt reactor (Mostra >>)
An Arbitrary Lagrangian-Eulerian, coupled neutronics-shock physics model for the analysis of shockwave implosion of solid fissile materials (Mostra >>)
Development of a reduced order model for fuel burnup analysis (Mostra >>)
Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core (Mostra >>)
Lattice boltzmann method applied to nuclear reactors-A systematic literature review (Mostra >>)
Preliminary analysis and design of the energy conversion system for the molten salt fast reactor (Mostra >>)
Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor (Mostra >>)
Reduced order modeling approach for parametrized thermal-hydraulics problems: inclusion of the energy equation in the POD-FV-ROM method (Mostra >>)
Stability analysis of a zero-dimensional model of PWR core using non-modal stability theory (Mostra >>)
Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2019 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Poster
A 3D MULTI-PHYSICS MODELLING OF THE TRIGA MARK II REACTOR (Mostra >>)
Contributo in Atti di convegno
Safety Parameters Uncertainty and Sensitivity Analysis for High Flux Reactor at Institut Laue Langevin (Mostra >>)
Sensitivity And Uncertainty Analysis of the TRIGA Mark II Reactor Using First and Second Order Perturbation Theory (Mostra >>)
Articoli su riviste
A CFD-based simulation tool for the stability analysis of natural circulation systems (Mostra >>)
A coupled neutronics shock physics solver: implementation of an SN neutron transport module (Mostra >>)
A new approach for nuclear reactor analysis based on complex network theory (Mostra >>)
An Arbitrary Lagrangian Eulerian solver for shock imploding fissile materials (Mostra >>)
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response (Mostra >>)
Development of a control-oriented power plant simulator for the molten salt fast reactor (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 >>)
Impact of uncertainties on the safety performances of the LBE-XADS concept nuclear reactor (Mostra >>)
Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches (Mostra >>)
Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects (Mostra >>)
Simplified 0-D semi-analytical model for fuel draining in molten salt reactors (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2018 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Abstract in Atti di convegno
A Reduced Order Kalman Filter for Computational Fluid-Dynamics Applications (Mostra >>)
Contributo in Atti di convegno
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 >>)
A multi-physics modelling approach for the analysis of Lead Fast Reactors (Mostra >>)
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 >>)
Application of the dynamic mode decomposition approach to the dispersion of radioactive contaminants in air (Mostra >>)
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts (Mostra >>)
Complete Thermal-Hydraulic Modelling of the Pavia TRIGA Mark II Research Reactor for the Study of the Natural Circulation Regime (Mostra >>)
Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project (Mostra >>)
Development of a Data-Driven Approach Based on Kalman Filtering for CFD Reactor Analysis (Mostra >>)
Dynamic Mode Decomposition for the Control of Nuclear Power Plants (Mostra >>)
Effects of a multi-physics coupling approach in Monte Carlo burnup calculations (Mostra >>)
Instabilities of burnup calculations in a SERPENT/OPENFOAM coupling (Mostra >>)
Articoli su riviste
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 >>)
A new model with Serpent for the first criticality benchmarks of the TRIGA Mark II reactor (Mostra >>)
A non-equilibrium control oriented model for the pressurizer dynamics (Mostra >>)
Adaptive simulation for failure identification in the Advanced Lead Fast Reactor European Demonstrator (Mostra >>)
An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events (Mostra >>)
MCNP model of L-54 M nuclear research reactor: development and preliminary verification (Mostra >>)
Monte Carlo integrated approach to radiological characterization for nuclear facilities decommissioning (Mostra >>)
Setting-up a control-oriented model for simulation of TRIGA Mark II dynamic response (Mostra >>)
Stability analysis of the Generation-IV nuclear reactors by means of the root locus criterion (Mostra >>)
Stability analysis of the Supercritical Water Reactor by means of the root locus criterion (Mostra >>)
The application of nodal method for dynamic analysis of TRIGA Mark II (Mostra >>)
manifesti v. 3.4.30 / 3.4.30
Area Servizi ICT
03/10/2022