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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 2023 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Articoli su riviste
Non-intrusive system state reconstruction from indirect measurements: A novel approach based on Hybrid Data Assimilation methods (Mostra >>)
Stabilization of Generalized Empirical Interpolation Method (GEIM) in presence of noise: A novel approach based on Tikhonov regularization (Mostra >>)
Status, Features, and Future Development of the LIFUS5/Mod4 Experimental Facility Design (Mostra >>)


Elenco delle pubblicazioni e dei prodotti della ricerca per l'anno 2022 (Mostra tutto | Nascondi tutto)
Tipologia Titolo Pubblicazione/Prodotto
Poster
Numerical simulation of the European 170GHz Gyrotron’s Magnetron Injection Gun in support of reduced order models development for control purposes (Mostra >>)
STEAM experimental facility a step forward for the development of the DEMO BoP water coolant technology (Mostra >>)
Status, features, and future development of the LIFUS5Mod4 facility design (Mostra >>)
The Design Of Water Loop Facility For Supporting The Water Coolant Lithium Lead Breeding Blanket Technology And Safety (Mostra >>)
Contributo in Atti di convegno
A Monte Carlo fuel assembly model validation adopting post irradiation experiment dataset (Mostra >>)
Advanced modelling and simulation of research reactors using Dynamic Mode Decomposition (Mostra >>)
Analysis of the void coefficient in Pavia TRIGA Mark-II reactor: Monte Carlo numerical evaluation and comparison with experimental data (Mostra >>)
Comparative analysis of different strategies exploiting the adjoint topology optimization method for enhancing the performance of a cooling device equipped with micro-channels (Mostra >>)
Development of an OpenFOAM multiphysics solver for solid fission products transport in the Molten Salt Fast Reactor (Mostra >>)
Dynamic Mode Decomposition analysis of a cooling channel of the TRIGA Mark II reactor (Mostra >>)
Dynamics of Natural Circulation in Presence of Distributed Heating: Results of the SAMOFAR CFD Simulation Campaign (Mostra >>)
Hybrid Data Assimilation methods: application to the DYNASTY experimental facility (Mostra >>)
Inviscid fluid simulation through Incompressible Schrödinger Flow method: a Finite Element approach (Mostra >>)
Large Eddy Simulation of the Dynamic Behaviour of the Dynasty Natural Circulation Loop (Mostra >>)
Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor (Mostra >>)
Multiphysics analysis of an in-core fission product removal system for the Molten Salt Fast Reactor (Mostra >>)
Numerical methodology for design and evaluation of natural circulation systems for MSR applications (Mostra >>)
Optical Performance of a Novel Tube-Bundle Cavity Receiver for Solar Parabolic Trough Collectors (Mostra >>)
Preliminary 1D modelling of the coupled DYNASTY-eDYNASTY experimental facility (Mostra >>)
Preliminary results of the experimental campaign conducted on the DYNASTY natural circulation loop (Mostra >>)
Sub-channel thermal hydraulics analysis of the 250 kW TRIGA Mark II nuclear reactor (Mostra >>)
Articoli su riviste
A neutronics optimization approach for preliminary design and safety of nuclear reactors for nuclear thermal propulsion (Mostra >>)
Biogeography-Based Optimization of the Resonator Cooling in a MW-Class Gyrotron for Fusion Applications (Mostra >>)
Damping signatures at JUNO, a medium-baseline reactor neutrino oscillation experiment (Mostra >>)
Detection of the Diffuse Supernova Neutrino Background with JUNO (Mostra >>)
Development and implementation of a multi-physics high fidelity model of the TRIGA mark II reactor (Mostra >>)
Feasibility of detecting B8 solar neutrinos at JUNO (Mostra >>)
JUNO Physics Prospects (Mostra >>)
JUNO physics and detector (Mostra >>)
Mass testing and characterization of 20-inch PMTs for JUNO (Mostra >>)
Modelling and CFD analysis of the DYNASTY loop facility (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 >>)
Object-oriented modeling, simulation and control of a 6-DoF parallel kinematic manipulator for remote handling in DONES facility (Mostra >>)
On the use of advanced nuclear cogeneration plant integrated into latent heat storage for district heating (Mostra >>)
Potential of Core-Collapse Supernova Neutrino Detection at JUNO (Mostra >>)
Prospects for detecting the diffuse supernova neutrino background with JUNO (Mostra >>)
Sensitivity-Analysis-Driven Surrogate Model for Molten Salt Reactors Control (Mostra >>)
Sub-percent precision measurement of neutrino oscillation parameters with JUNO* (Mostra >>)
Towards net-zero emissions through the hybrid SMR-solar cogeneration plant equipped with modular PCM storage system for seawater desalination (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 >>)
manifesti v. 3.5.4 / 3.5.4
Area Servizi ICT
07/02/2023