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List of works by Antonio Cammi

A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics

article

A Mass Conservative Kalman Filter Algorithm for Computational Thermo-Fluid Dynamics

scientific article published on 08 November 2018

A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants

article

A Preliminary Approach to the Dynamic Behaviour of Circulating Fuel Reactors for Generation IV

A Preliminary Study of the MSFR Dynamics

A Simplified Model for a Preliminary Study of the Dynamic Behaviour of a Small Gen IV LFR DEMO

A generalized approach to heat transfer in pipe flow with internal heat generation

A model predictive control approach for the Italian LBE–XADS

article

A multi-physics modelling approach to the dynamics of Molten Salt Reactors

A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel

article

A new model with Serpent for the first criticality benchmarks of the TRIGA Mark II reactor

A non-equilibrium control oriented model for the pressurizer dynamics

A preliminary approach to the ALFRED reactor control strategy

A preliminary approach to the MSFR control issues

A reduced order model for investigating the dynamics of the Gen-IV LFR coolant pool

scholarly article by Stefano Lorenzi et al published June 2017 in Applied Mathematical Modelling

A scheme of correlation for frictional pressure drop in steam–water two-phase flow in helicoidal tubes

scholarly article by Marco Colombo et al published February 2015 in Chemical Engineering Science

A zero dimensional model for simulation of TRIGA Mark II dynamic response

An approach for the modelling and the analysis of the MSR thermo-hydrodynamic behaviour

An approach to the MSR dynamics and stability analysis

article published in 2013

An ensemble approach to sensor fault detection and signal reconstruction for nuclear system control

An object-oriented approach to simulation of IRIS dynamic response

Analysis of different containment models for IRIS small break LOCA, using GOTHIC and RELAP5 codes

Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models

Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure

scholarly article by Carlo Fiorina et al published March 2013 in Annals of Nuclear Energy

Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor

Assessment of Different Turbulence Models in Helically Coiled Pipes Through Comparison With Experimental Data

Biogeography-Based Optimization of the Resonator Cooling in a MW-Class Gyrotron for Fusion Applications

scientific article published in 2022

CFD study of an air–water flow inside helically coiled pipes

Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches

Characterization of the TRIGA Mark II reactor full-power steady state

Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics

Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor

article published in 2015

Development of a Spatial Neutronics Model for Control-Oriented Dynamics Simulation

article

Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor

article

Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis

article

Development of the ALFRED reactor full power mode control system

article

Dimensional effects in the modelling of MSR dynamics: Moving on from simplified schemes of analysis to a multi-physics modelling approach

article published in 2012

Dynamic stability of natural circulation loops for single phase fluids with internal heat generation

scholarly article by D.E. Ruiz et al published April 2015 in Chemical Engineering Science

Experimental and numerical study of the laminar flow in helically coiled pipes

Experimental and theoretical studies on density wave instabilities in helically coiled tubes

Fuel burnup analysis of the TRIGA Mark II reactor at the University of Pavia

Gamma dose from activation of internal shields in IRIS reactor.

scientific article published in January 2005

Gas transfer model to design a ventilator for neonatal total liquid ventilation

scientific article published on 13 October 2015

Investigation of the MSFR core physics and fuel cycle characteristics

Local Fusion of an Ensemble of Models for the Reconstruction of Faulty Signals

Measurement and simulation of the neutron flux distribution in the TRIGA Mark II reactor core

article published in 2015

Modelling and analysis of the MSFR transient behaviour

Modelling and control strategy of the Italian LBE-XADS

article

Modelling of Heat Transfer Phenomena for Vertical and Horizontal Configurations of In-Pool Condensers and Comparison with Experimental Findings

Molten salt mixture properties in RELAP5 code for thermodynamic solar applications

Neutrino physics with JUNO

scientific article

Object-Oriented Modeling and simulation of a TRIGA reactor plant with Dymola

article

Object-oriented modelling and simulation for the ALFRED dynamics

POD-Galerkin method for finite volume approximation of Navier–Stokes and RANS equations

Petri-net based modelling approach for ALFRED reactor operation and control system design

Preliminary Analysis of the MSFR Fuel Cycle Using Modified-EQL3D Procedure

RELAP5/MOD3.3 study on density wave instabilities in single channel and two parallel channels

Reduced Basis Approaches in Time-Dependent Non-Coercive Settings for Modelling the Movement of Nuclear Reactor Control Rods

Study of a Low-power, Fast-neutron-based ADS

Study of an intrinsically safe infrastructure for training and research on nuclear technologies

Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor

Time-domain linear and non-linear studies on density wave oscillations

Transfer function modelling of the Lead-cooled Fast Reactor (LFR) dynamics