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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)

Professor's office hours
Ingegneria Nucleare, via Ponzio 34/3, Milano Leonardo----TuesdayFrom 14:00
To 16:00
02.2399.6332--Si prega di fissare anticipatamente l'appuntamento.
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 2023 (Show all details | Hide all details)
Type Title of the Publicaiton/Product
Conference proceedings
Indirect Field Reconstruction and Sensor Positioning in Circulating Fuel Reactors using Data-Driven Model Order Reduction (Show >>)
Journal Articles
A set of transient correlations for fast and unprotected loss of flow accident in VVER-1000 reactor using single-heated channel approach and Gene Expression Programming (Show >>)
ALFRED reactor and hybrid systems: A test case (Show >>)
Hybrid Data Assimilation methods, Part II: Application to the DYNASTY experimental facility (Show >>)
Hybrid data assimilation methods, Part I: Numerical comparison between GEIM and PBDW (Show >>)
Non-intrusive system state reconstruction from indirect measurements: A novel approach based on Hybrid Data Assimilation methods (Show >>)
Stabilization of Generalized Empirical Interpolation Method (GEIM) in presence of noise: A novel approach based on Tikhonov regularization (Show >>)
Status, Features, and Future Development of the LIFUS5/Mod4 Experimental Facility Design (Show >>)

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