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Prof. Antonio Cammi
Politecnico di Milano - Department of Energy

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Research Keywords & Expertise

0 Nuclear Energy
0 Fluid and Thermal science
0 Nuclear engineering and nuclear technology
0 Modelling and simulation of energy systems
0 Simulation and control

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Nuclear Energy
Modelling and simulation of energy systems
Simulation and control
Nuclear engineering and nuclear technology

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Journal article
Published: 31 July 2021 in Progress in Nuclear Energy
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The development of a new generation of reactor presents several modelling challenges that cannot be effectively addressed by traditional tools used for Light Water Reactors. Multi-physics approaches allow for a comprehensive modeling of reactor cores, as they intrinsically couple the involved physics (i.e. fluid-dynamics, heat transfer, neutronics, thermo-mechanics), but require intense computational efforts that preclude their use in reactor control applications. This work aims at applying a Reduced Order Model (ROM) technique to multi-physics modelling. Such objective is achieved through a ROM technique previously used for Navier-Stokes equations and thermal-hydraulics problems (POD-FV-ROM). The technique used in this article, is built on a modeling framework developed ad-hoc for the Finite Volume (FV) scheme and relies on the Proper Orthogonal Decomposition (POD) and the Method of Snapshots. The reduced order multi-physics approach outlined in this work has been tested with success on a Lid-Driven-Cavity-based homogeneous reactor model. Reduced-order simulations have reproduced accurately the full order velocity, temperature, neutron flux and precursor concentration fields, resulting in relative L2 norms of the differences between full order and reduced order simulations below 1 % for all the considered fields.

ACS Style

Lorenzo Vergari; Antonio Cammi; Stefano Lorenzi. Reduced order modeling for coupled thermal-hydraulics and reactor physics problems. Progress in Nuclear Energy 2021, 140, 103899 .

AMA Style

Lorenzo Vergari, Antonio Cammi, Stefano Lorenzi. Reduced order modeling for coupled thermal-hydraulics and reactor physics problems. Progress in Nuclear Energy. 2021; 140 ():103899.

Chicago/Turabian Style

Lorenzo Vergari; Antonio Cammi; Stefano Lorenzi. 2021. "Reduced order modeling for coupled thermal-hydraulics and reactor physics problems." Progress in Nuclear Energy 140, no. : 103899.

Journal article
Published: 02 July 2021 in Nuclear Engineering and Design
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Various passive safety systems have been developed for advanced nuclear reactors. The use of natural driving force for passive systems requires accurate assessment of reliability and performance. Sensitivity analysis is an efficient technique to test the reliability and performance of a safety system, and in order to improve the computational efficiency, the adjoint-based sensitivity method has been introduced. The present study aims to develop an adjoint-based sensitivity method to evaluate the sensitivity of natural circulation system using high-Pr fluid, and to assess its applicability to the experimental facility developed in UNIST. The conservation equations for a closed rectangular loop are written, and the corresponding adjoint system is developed based on the Lagrangian approach. Three different functionals are evaluated which represent thermal-hydraulics and heat transfer performance with respect to various input parameters. The developed adjoint method shows reasonable accuracy in the sensitivity analysis compared with other methods, while significantly reducing the computational time. Following sensitivity analyses using various design parameters assess the sensitivity of natural circulation mass flux, temperature distribution, and Nusselt number. Three different system conditions are imposed to investigate the effects of (i) the implementation of temperature-dependent fluid properties, (ii) the orientations of the heat exchanger and (iii) the operating temperature range, on the entire system reliability. It is found that the variation of fluid properties with respect to the temperature has an important effect on the stability of heat transfer performance in the system. Finally, the advantages in using high-Pr fluids for natural circulation heat transport system is verified by comparing the sensitivities of Nusselt number for different fluids with different Prandtl numbers. The outputs of this study are expected to provide the assessment of the reliability and performance of natural circulation system using molten salt, which can be used for further design studies on molten salt system with low computational burden. Furthermore, this paper demonstrate the applicability of the adjoint-based method for molten salt system applications.

ACS Style

Seok Bin Seo; In Cheol Bang; Hisashi Ninokata; Antonio Cammi. Application of adjoint-based sensitivity analysis to natural circulation of high-Pr fluid inside heat transport system. Nuclear Engineering and Design 2021, 381, 111349 .

AMA Style

Seok Bin Seo, In Cheol Bang, Hisashi Ninokata, Antonio Cammi. Application of adjoint-based sensitivity analysis to natural circulation of high-Pr fluid inside heat transport system. Nuclear Engineering and Design. 2021; 381 ():111349.

Chicago/Turabian Style

Seok Bin Seo; In Cheol Bang; Hisashi Ninokata; Antonio Cammi. 2021. "Application of adjoint-based sensitivity analysis to natural circulation of high-Pr fluid inside heat transport system." Nuclear Engineering and Design 381, no. : 111349.

Original research article
Published: 29 June 2021 in Frontiers in Energy Research
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Nuclear reactor modeling has been shifting, over the last decades, towards full-core multiphysics analysis due to the ever-increasing safety requirements and complexity of the designs of innovative systems. This is particularly true for liquid-fuel reactor concepts such as the Molten Salt Fast Reactor (MSFR), given their strong intrinsic coupling between thermal-hydraulics, neutronics and fuel chemistry. In the MSFR, fission products (FPs) are originated within the liquid fuel and are carried by the fuel flow all over the reactor core and through pumping and heat exchange systems. Some of FP species, in the form of solid precipitates, can represent a major design and safety challenge, e.g., due to deposition on solid boundaries, and their distribution in the core is relevant to the design and safety analysis of the reactor. In this regard it is essential, both for the design and the safety assessment of the reactor, the capability to model the transport of solid FPs and their deposition to the boundary (e.g., wall or heat exchanger structures). To this aim, in this study, models of transport of solid FPs in the MSFR are developed and verified. An Eulerian single-phase transport model is developed and integrated in a consolidated multiphysics model of the MSFR based on the open-source CFD library OpenFOAM. In particular, general mixed-type deposition boundary conditions are considered, to possibly describe different kinds of particle-wall interaction mechanisms. For verification purposes, analytical solutions for simple case studies are derived ad hoc based on the extension of the classic Graetz problem to linear decay, distributed source terms and mixed-type boundary conditions. The results show excellent agreement between the two models, and highlight the effects of decay and deposition phenomena of various intensity. The resulting approach constitutes a computationally efficient tool to extend the capabilities of CFD-based multiphysics MSFR calculations towards the simulation of solid fission products transport.

ACS Style

Andrea Di Ronco; Stefano Lorenzi; Francesca Giacobbo; Antonio Cammi. An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purposes. Frontiers in Energy Research 2021, 9, 1 .

AMA Style

Andrea Di Ronco, Stefano Lorenzi, Francesca Giacobbo, Antonio Cammi. An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purposes. Frontiers in Energy Research. 2021; 9 ():1.

Chicago/Turabian Style

Andrea Di Ronco; Stefano Lorenzi; Francesca Giacobbo; Antonio Cammi. 2021. "An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purposes." Frontiers in Energy Research 9, no. : 1.

Journal article
Published: 08 April 2021 in Energies
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In the framework of the ITER (International Thermonuclear Experimental Reactor) project, one of the key components of the reactor is the ECRH (Electron Cyclotron Resonance Heating). This system has the duty to heat the plasma inside the tokamak, using high frequency and power radio waves, produced by sets of 1MW gyrotrons. One of the main issues related to the gyrotron operation is the output power drop that happens right after the beginning of a pulse. In this work, we study the underlying phenomena that cause the power drop, focusing on the gyrotron’s MIG (Magnetron Injection Gun) of the 1MW, 170 GHz European Gyrotron prototype for ITER. It is shown how the current emission and the temperature of the emitter are tightly bound, and how their interaction causes the power drop, observed experimentally. Furthermore, a simple yet effective lumped-parameter model to describe the MIG’s cathode thermal dynamics is developed, which is able to predict the power output of the gyrotron by simulating the propagation of the heat inside this component. The model is validated against test results, showing a good capability to reproduce the measured behavior of the system, while still being open to further improvements.

ACS Style

Nicolò Badodi; Antonio Cammi; Alberto Leggieri; Francisco Sanchez; Laura Savoldi. A New Lumped Approach for the Simulation of the Magnetron Injection Gun for MegaWatt-Class EU Gyrotrons. Energies 2021, 14, 2068 .

AMA Style

Nicolò Badodi, Antonio Cammi, Alberto Leggieri, Francisco Sanchez, Laura Savoldi. A New Lumped Approach for the Simulation of the Magnetron Injection Gun for MegaWatt-Class EU Gyrotrons. Energies. 2021; 14 (8):2068.

Chicago/Turabian Style

Nicolò Badodi; Antonio Cammi; Alberto Leggieri; Francisco Sanchez; Laura Savoldi. 2021. "A New Lumped Approach for the Simulation of the Magnetron Injection Gun for MegaWatt-Class EU Gyrotrons." Energies 14, no. 8: 2068.

Journal article
Published: 08 April 2021 in Expert Systems with Applications
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In this paper, a method based on a backpropagation neural network (BPNN) is proposed to calculate the exposure buildup factor (BD) of a point isotropic source in an infinite homogeneous medium under arbitrary energy and mean free path (mfp). The results obtained for aluminum, iron, lead, and concrete based on BPNN are compared to ANSI/ANS-6.4.3 standard data, the results calculated by MCNP 5 Monte Carlo code, and a geometric progression (G-P) fitting formula, and show that the BD calculated by the BPNN model is more consistent with the ANS standard data. This method improves the calculation and fitting effect of BD compared to other methods. This paper proposes a systematic process combining a Monte Carlo method and BPNN to calculate and predict the BD of new materials under different energy and mfp, thus replacing the G-P fitting formula and improving calculation accuracy.

ACS Style

Runkai Chen; Antonio Cammi; Marcus Seidl; Rafael Macian-Juan; Xiang Wang. Calculation of gamma-ray exposure buildup factor based on backpropagation neural network. Expert Systems with Applications 2021, 177, 115004 .

AMA Style

Runkai Chen, Antonio Cammi, Marcus Seidl, Rafael Macian-Juan, Xiang Wang. Calculation of gamma-ray exposure buildup factor based on backpropagation neural network. Expert Systems with Applications. 2021; 177 ():115004.

Chicago/Turabian Style

Runkai Chen; Antonio Cammi; Marcus Seidl; Rafael Macian-Juan; Xiang Wang. 2021. "Calculation of gamma-ray exposure buildup factor based on backpropagation neural network." Expert Systems with Applications 177, no. : 115004.

Research article
Published: 30 March 2021 in International Journal for Numerical Methods in Engineering
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This paper presents two extensions of the Empirical Interpolation Method (EIM) designed to deal with vector interpolation problems. These Reduced Order Modeling (ROM) techniques are aimed at exploiting point‐wise (vector) measurements to obtain the unknown field reconstruction and they are preferred to other, more efficient, techniques as the Proper Orthogonal Decomposition (POD) because of their intrinsic capability to identify measurement positions and to perform field reconstruction. The "EIM‐orto" method implements rotation matrix coefficients and should be intended as a composition of rotations and dilatations of the vector basis functions. The "EIM‐orto" implements diagonal matrices coefficients and can be intended as the interpolation, component by component, of the unknown vector field, projected on a fixed reference system. The two techniques are tested over the lid‐driven cavity benchmark, in laminar conditions. The results obtained on this study case highlight how the EIM‐orto interpolation does not allow a reliable reconstructions, while the EIM‐roto interpolation allows reconstruction performances close to the POD ones (here used as reference method). In particular, the worst reconstruction error, i.e. the maximum L2 – norm of the residuals, decreases exponentially, reaching 5% with 25 basis functions. This result can be consider satisfactory, considering the nature of the problem.

ACS Style

Francesco A. B. Silva; Stefano Lorenzi; Antonio Cammi. An empirical interpolation method for two‐dimensional vector fields and vector measurements. International Journal for Numerical Methods in Engineering 2021, 1 .

AMA Style

Francesco A. B. Silva, Stefano Lorenzi, Antonio Cammi. An empirical interpolation method for two‐dimensional vector fields and vector measurements. International Journal for Numerical Methods in Engineering. 2021; ():1.

Chicago/Turabian Style

Francesco A. B. Silva; Stefano Lorenzi; Antonio Cammi. 2021. "An empirical interpolation method for two‐dimensional vector fields and vector measurements." International Journal for Numerical Methods in Engineering , no. : 1.

Conference paper
Published: 27 March 2021 in Lecture Notes in Civil Engineering
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Response to the increasingly serious problems of global water risk in many arid regions of the planet has become a critical concern to governments. One of the best solutions to overcome the water shortage is using large-scale seawater desalination facilities. Currently, in many Western Asia countries with vast non-renewable resources, the fossil-fuel based power plants are considered as the dominant energy sources for driving the desalination plants (DPs). Considering numerous problems with fossil fuels, most of the water-scarce governments over the world are developing the long-term energy strategy of the country based on using sustainable and renewable energies. In this study, a techno-economic evaluation of hybrid DP powered by the Advanced Lead Fast Reactor European Demonstrator (ALFRED) and solar power plant (SPP), equipped with latent thermal storage system is conducted. The obtained results express that almost, 60% of required thermal energy for driving the thermal DP can be obtained by SPP.

ACS Style

Khashayar Sadeghi; Seyed Hadi Ghazaie; Riccardo Chebac; Ekaterina Sokolova; Evgeniy Fedorovich; Antonio Cammi; Marco Enrico Ricotti. 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. Lecture Notes in Civil Engineering 2021, 85 -96.

AMA Style

Khashayar Sadeghi, Seyed Hadi Ghazaie, Riccardo Chebac, Ekaterina Sokolova, Evgeniy Fedorovich, Antonio Cammi, Marco Enrico Ricotti. 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. Lecture Notes in Civil Engineering. 2021; ():85-96.

Chicago/Turabian Style

Khashayar Sadeghi; Seyed Hadi Ghazaie; Riccardo Chebac; Ekaterina Sokolova; Evgeniy Fedorovich; Antonio Cammi; Marco Enrico Ricotti. 2021. "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." Lecture Notes in Civil Engineering , no. : 85-96.

Journal article
Published: 25 February 2021 in Fusion Engineering and Design
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The Water Cooled Lithium Lead Test Blanket System (WCLL TBS) is one of the EU Test Blanket Systems candidate for being installed and operated in ITER. In view of its Conceptual Design Review by F4E and ITER Organization (IO), planned for mid-September 2020, several technical activities have been performed in the areas of WCLL TBS Ancillary Systems design. In this article the outcomes of the conceptual design phase of the four main Ancillary Systems of WCLL TBS, namely the Water Cooling System (WCS), the Coolant Purification System (CPS), the PbLi loop and the Tritium Extraction System (TES), are reported and critically discussed. In particular, for each Ancillary System hereafter are reported: i) a short design description, including the conceptual design of their main components together with their operative conditions under the so-called Normal Operational State (NOS), ii) the ESP-ESPN classification for their main components, and iii) their arrangement and integration in the assigned ITER areas (PC#16, Vertical Shaft, TCWS Vault, Galleries and Tritium Process Room).

ACS Style

Amelia Tincani; Pietro Arena; Maurizio Bruzzone; Ilenia Catanzaro; Cristiano Ciurluini; Alessandro Del Nevo; Pietro Alessandro Di Maio; Ruggero Forte; Fabio Giannetti; Stefano Lorenzi; Emanuela Martelli; Carlos Moreno; Rocco Mozzillo; Carlos Ortiz; Ferruccio Paoletti; Veronica Pierantoni; Italo Ricapito; Gandolfo Alessandro Spagnuolo; Andrea Tarallo; Claudio Tripodo; Antonio Cammi; Marco Utili; Konstantina Voukelatou; Erik Walcz; Balazs Lesko; Jessica Korzeniowska; Pierluigi Chiovaro; Vincenzo Narcisi. Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System. Fusion Engineering and Design 2021, 167, 112345 .

AMA Style

Amelia Tincani, Pietro Arena, Maurizio Bruzzone, Ilenia Catanzaro, Cristiano Ciurluini, Alessandro Del Nevo, Pietro Alessandro Di Maio, Ruggero Forte, Fabio Giannetti, Stefano Lorenzi, Emanuela Martelli, Carlos Moreno, Rocco Mozzillo, Carlos Ortiz, Ferruccio Paoletti, Veronica Pierantoni, Italo Ricapito, Gandolfo Alessandro Spagnuolo, Andrea Tarallo, Claudio Tripodo, Antonio Cammi, Marco Utili, Konstantina Voukelatou, Erik Walcz, Balazs Lesko, Jessica Korzeniowska, Pierluigi Chiovaro, Vincenzo Narcisi. Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System. Fusion Engineering and Design. 2021; 167 ():112345.

Chicago/Turabian Style

Amelia Tincani; Pietro Arena; Maurizio Bruzzone; Ilenia Catanzaro; Cristiano Ciurluini; Alessandro Del Nevo; Pietro Alessandro Di Maio; Ruggero Forte; Fabio Giannetti; Stefano Lorenzi; Emanuela Martelli; Carlos Moreno; Rocco Mozzillo; Carlos Ortiz; Ferruccio Paoletti; Veronica Pierantoni; Italo Ricapito; Gandolfo Alessandro Spagnuolo; Andrea Tarallo; Claudio Tripodo; Antonio Cammi; Marco Utili; Konstantina Voukelatou; Erik Walcz; Balazs Lesko; Jessica Korzeniowska; Pierluigi Chiovaro; Vincenzo Narcisi. 2021. "Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System." Fusion Engineering and Design 167, no. : 112345.

Journal article
Published: 18 February 2021 in Chemical Engineering Science
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Natural circulation is exploited in nuclear systems to passively remove power in case of accident scenarios. In this regard, the DYNASTY experimental facility at Politecnico di Milano has been setup to increase the knowledge on single-phase, buoyancy-driven systems in the presence of distributed heating. In this paper, the development of a computational fluid dynamics (CFD) model of DYNASTY is presented, focusing on the capability of CFD to assess the dynamic behavior of the facility. The large eddy simulation (LES) model takes into account both the fluid and the solid regions, with heat generation and 3D heat conduction resolved in the pipe walls. The study, conducted using OpenFOAM, shows (i) the capability of reproducing stable and unstable transients of DYNASTY, (ii) new observations on the features of flow reversals during unstable transients, (iii) the suitability and the advantages of LES for the prediction of the specific features of natural circulation systems.

ACS Style

A. Battistini; A. Cammi; S. Lorenzi; M. Colombo; M. Fairweather. Development of a CFD – LES model for the dynamic analysis of the DYNASTY natural circulation loop. Chemical Engineering Science 2021, 237, 116520 .

AMA Style

A. Battistini, A. Cammi, S. Lorenzi, M. Colombo, M. Fairweather. Development of a CFD – LES model for the dynamic analysis of the DYNASTY natural circulation loop. Chemical Engineering Science. 2021; 237 ():116520.

Chicago/Turabian Style

A. Battistini; A. Cammi; S. Lorenzi; M. Colombo; M. Fairweather. 2021. "Development of a CFD – LES model for the dynamic analysis of the DYNASTY natural circulation loop." Chemical Engineering Science 237, no. : 116520.

Journal article
Published: 18 January 2021 in Nuclear Engineering and Design
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In this paper, different control strategies for the full-power mode operation (i.e. from 50% to 100% of reactor rated power) of the MSFR are identified, developed, and their performances tested, starting from the results of a MSFR power plant simulator. In order to support the qualitative results gained from the free-dynamics outcomes, a technique known as Relative Gain Array is employed to obtain a quantitative measure of the degree of interaction between the various input and output variables, and to identify the most favorable couplings. In the development of control strategies, particular attention is placed on several specific aspects, in particular the load-following capabilities of the power plant, the need to keep the molten salts temperatures within a rather narrow window to avoid boiling or freezing risks during operational transients, and the need to maintain the operating conditions of the energy conversion system as constant as possible. Four different decentralized-feedback control strategies are implemented – with different number of controlled outputs – by employing conventional PID controllers, which are designed and tuned with appropriate phase and gain margins to account for modeling uncertainties. The different control strategies are then tested on the power plant simulator in two typical controlled operational transients, highlighting the very promising behavior of the MSFR in terms of load-following capabilities. The results of the present work will also provide valuable insights in support to the optimization and finalization of the MSFR power plant design.

ACS Style

Claudio Tripodo; Stefano Lorenzi; Antonio Cammi. Definition of model-based control strategies for the Molten Salt Fast Reactor nuclear power plant. Nuclear Engineering and Design 2021, 373, 111015 .

AMA Style

Claudio Tripodo, Stefano Lorenzi, Antonio Cammi. Definition of model-based control strategies for the Molten Salt Fast Reactor nuclear power plant. Nuclear Engineering and Design. 2021; 373 ():111015.

Chicago/Turabian Style

Claudio Tripodo; Stefano Lorenzi; Antonio Cammi. 2021. "Definition of model-based control strategies for the Molten Salt Fast Reactor nuclear power plant." Nuclear Engineering and Design 373, no. : 111015.

Journal article
Published: 15 December 2020 in Sustainability
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The unique design features of the molten salt fast reactor (MSFR) should enable higher coolant temperatures than in conventional water reactors, with a significant improvement in the achievable thermodynamic performance. The use of a molten salt as both fuel and coolant, however, poses several advanced heat transfer challenges, such as the design of innovative heat exchangers and energy conversion systems. In this work, we address a preliminary but quantitative analysis of the energy conversion system for the MSFR, based on reference design data from the SAMOFAR H2020-EURATOM project. We consider three main technologies, i.e., the supercritical steam cycle, the closed helium cycle and the helium/steam combined cycle. Preliminary design results are presented for each technology, based on a simplified modelling approach. The considered cycles show promising efficiency improvements, with the best performance being proven by the supercritical steam cycle. The analysis also highlights the critical issue related to the risk of freezing of the molten salts within the secondary heat exchangers, due to the low inlet temperatures of the working fluids. Results show potential incompatibility between the freezing point of molten salts and the temperatures typical of steam cycles, while helium cycles offer the best chances of freezing avoidance. The combined cycle promises intermediate performance in terms of thermodynamic efficiency and thermal compatibility with molten salts comparable with closed helium cycles.

ACS Style

Andrea Di Ronco; Francesca Giacobbo; Guglielmo Lomonaco; Stefano Lorenzi; Xiang Wang; Antonio Cammi. Preliminary Analysis and Design of the Energy Conversion System for the Molten Salt Fast Reactor. Sustainability 2020, 12, 10497 .

AMA Style

Andrea Di Ronco, Francesca Giacobbo, Guglielmo Lomonaco, Stefano Lorenzi, Xiang Wang, Antonio Cammi. Preliminary Analysis and Design of the Energy Conversion System for the Molten Salt Fast Reactor. Sustainability. 2020; 12 (24):10497.

Chicago/Turabian Style

Andrea Di Ronco; Francesca Giacobbo; Guglielmo Lomonaco; Stefano Lorenzi; Xiang Wang; Antonio Cammi. 2020. "Preliminary Analysis and Design of the Energy Conversion System for the Molten Salt Fast Reactor." Sustainability 12, no. 24: 10497.

Journal article
Published: 30 November 2020 in Sustainability
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In the present work, a online data assimilation approach, based on the Kalman filter algorithm, is proposed for the source term reconstruction in accidental events with dispersion of radioactive agents in air. For this purpose a Gaussian plume model of dispersion in air is embedded in the Kalman filter algorithm to estimate unknown scenario parameters, such as the coordinates and the intensity of the source, on the basis of measurements collected by a mobile sensor. The approach was tested against pseudo-experimental data produced with both the Gaussian plume model and the Lagrangian puff model SCIPUFF. The results show the good capabilities of the proposed approach in retrieving the values of the unknown parameters when (i) one or more release parameters are poorly known and (ii) a sufficient number of experimental measurements describing the evolution of the dispersion process can be collected in a short time by means of mobile sensors. Thanks to its flexibility and computational efficiency, and due to the exploitation of the Kalman filter potentialities through the use of a simplified model of dispersion in air, the proposed approach can constitute a useful tool for the management of emergency scenarios.

ACS Style

Andrea Di Ronco; Francesca Giacobbo; Antonio Cammi. A Kalman Filter-Based Approach for Online Source-Term Estimation in Accidental Radioactive Dispersion Events. Sustainability 2020, 12, 10003 .

AMA Style

Andrea Di Ronco, Francesca Giacobbo, Antonio Cammi. A Kalman Filter-Based Approach for Online Source-Term Estimation in Accidental Radioactive Dispersion Events. Sustainability. 2020; 12 (23):10003.

Chicago/Turabian Style

Andrea Di Ronco; Francesca Giacobbo; Antonio Cammi. 2020. "A Kalman Filter-Based Approach for Online Source-Term Estimation in Accidental Radioactive Dispersion Events." Sustainability 12, no. 23: 10003.

Review
Published: 22 September 2020 in Sustainability
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Nuclear engineering requires computationally efficient methods to simulate different components and systems of plants. The Lattice Boltzmann Method (LBM), a numerical method with a mesoscopic approach to Computational Fluid Dynamic (CFD) derived from the Boltzmann equation and the Maxwell–Boltzmann distribution, can be an adequate option. The purpose of this paper is to present a review of the recent applications of the Lattice Boltzmann Method in nuclear engineering research. A systematic literature review using three databases (Web of Science, Scopus, and ScienceDirect) was done, and the items found were categorized by the main research topics into computational fluid dynamics and neutronic applications. The features of the problem addressed, the characteristics of the numerical method, and some relevant conclusions of each study are resumed and presented. A total of 45 items (25 for computational fluid dynamics applications and 20 for neutronics) was found on a wide range of nuclear engineering problems, including thermal flow, turbulence mixing of coolant, sedimentation of impurities, neutron transport, criticality problem, and other relevant issues. The LBM results in being a flexible numerical method capable of integrating multiphysics and hybrid schemes, and is efficient for the inner parallelization of the algorithm that brings a widely applicable tool in nuclear engineering problems. Interest in the LBM applications in this field has been increasing and evolving from early stages to a mature form, as this review shows.

ACS Style

Johan Bocanegra Cifuentes; Davide Borelli; Antonio Cammi; Guglielmo Lomonaco; Mario Misale. Lattice Boltzmann Method Applied to Nuclear Reactors—A Systematic Literature Review. Sustainability 2020, 12, 7835 .

AMA Style

Johan Bocanegra Cifuentes, Davide Borelli, Antonio Cammi, Guglielmo Lomonaco, Mario Misale. Lattice Boltzmann Method Applied to Nuclear Reactors—A Systematic Literature Review. Sustainability. 2020; 12 (18):7835.

Chicago/Turabian Style

Johan Bocanegra Cifuentes; Davide Borelli; Antonio Cammi; Guglielmo Lomonaco; Mario Misale. 2020. "Lattice Boltzmann Method Applied to Nuclear Reactors—A Systematic Literature Review." Sustainability 12, no. 18: 7835.

Journal article
Published: 19 September 2020 in Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
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Jiangmen Underground Neutrino Observatory (JUNO) is a next generation liquid scintillator neutrino experiment under construction phase in South China. Thanks to the anti-neutrinos produced by the nearby nuclear power plants, JUNO will be able to study the neutrino mass hierarchy, one of the open key questions in neutrino physics. One key ingredient for a successful measurement is to use high speed, high resolution sampling electronics located very close to the detector signal. Linearity in the response of the electronics is another important ingredient for the success of the experiment. During the initial design phase of the electronics, a custom design with the Front-End and Read-Out electronics located very close to the detector analog signal has been developed and successfully tested. The present paper describes the electronics structure and the first tests performed on the prototypes. The electronics prototypes have been tested and they show good linearity response, with a maximum deviation of 1.3% over the full dynamic range (1-1000 p.e.), fulfilling the JUNO experiment requirements.

ACS Style

M. Bellato; A. Bergnoli; A. Brugnera; S. Chen; Z. Chen; B. Clerbaux; F. Dal Corso; D. Corti; J. Dong; G. Galet; A. Garfagnini; A. Giaz; G. Gong; C. Grewing; J. Hu; R. Isocrate; X. Jiang; F. Li; I. Lippi; F. Marini; Z. Ning; A. Olshevskiy; D. Pedretti; P.A. Petitjean; M. Robens; V. Shutov; A. Stahl; J. Steinmann; Y. Sun; S. van Waasen; Y. Wang; Z. Wang; W. Wei; X. Yan; Y. Yang; A. Aiello; A. Andronico; V. Antonelli; W. Bandini; A. Brigatti; A. Barresi; A. Budano; R. Bruno; A. Cabrera; A. Cammi; R. Caruso; D. Chiesa; C. Clementi; S. Costa; X. Ding; S. Dusini; A. Fabbri; M. Fargetta; G. Fiorentini; R. Ford; A. Formozov; M. Giammarchi; M. Grassi; C. Landini; P. Lombardi; C. Lombardo; Y. Malyshkin; F. Mantovani; S.M. Mari; C. Martellini; A. Martini; E. Meroni; M. Mezzetto; L. Miramonti; P. Montini; M. Montuschi; M. Nastasi; F. Ortica; A. Paoloni; S. Parmeggiano; N. Pelliccia; E. Previtali; G. Ranucci; D. Riondino; A.C. Re; B. Ricci; A. Romani; P. Saggese; G. Salamanna; F.H. Sawy; A. Serafini; G. Settanta; C. Sirignano; M. Sisti; L. Stanco; V. Strati; C. Tuvé; G. Verde; L. Votano; J. Zhang. Embedded readout electronics R&D for the large PMTs in the JUNO experiment. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 2020, 985, 164600 .

AMA Style

M. Bellato, A. Bergnoli, A. Brugnera, S. Chen, Z. Chen, B. Clerbaux, F. Dal Corso, D. Corti, J. Dong, G. Galet, A. Garfagnini, A. Giaz, G. Gong, C. Grewing, J. Hu, R. Isocrate, X. Jiang, F. Li, I. Lippi, F. Marini, Z. Ning, A. Olshevskiy, D. Pedretti, P.A. Petitjean, M. Robens, V. Shutov, A. Stahl, J. Steinmann, Y. Sun, S. van Waasen, Y. Wang, Z. Wang, W. Wei, X. Yan, Y. Yang, A. Aiello, A. Andronico, V. Antonelli, W. Bandini, A. Brigatti, A. Barresi, A. Budano, R. Bruno, A. Cabrera, A. Cammi, R. Caruso, D. Chiesa, C. Clementi, S. Costa, X. Ding, S. Dusini, A. Fabbri, M. Fargetta, G. Fiorentini, R. Ford, A. Formozov, M. Giammarchi, M. Grassi, C. Landini, P. Lombardi, C. Lombardo, Y. Malyshkin, F. Mantovani, S.M. Mari, C. Martellini, A. Martini, E. Meroni, M. Mezzetto, L. Miramonti, P. Montini, M. Montuschi, M. Nastasi, F. Ortica, A. Paoloni, S. Parmeggiano, N. Pelliccia, E. Previtali, G. Ranucci, D. Riondino, A.C. Re, B. Ricci, A. Romani, P. Saggese, G. Salamanna, F.H. Sawy, A. Serafini, G. Settanta, C. Sirignano, M. Sisti, L. Stanco, V. Strati, C. Tuvé, G. Verde, L. Votano, J. Zhang. Embedded readout electronics R&D for the large PMTs in the JUNO experiment. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2020; 985 ():164600.

Chicago/Turabian Style

M. Bellato; A. Bergnoli; A. Brugnera; S. Chen; Z. Chen; B. Clerbaux; F. Dal Corso; D. Corti; J. Dong; G. Galet; A. Garfagnini; A. Giaz; G. Gong; C. Grewing; J. Hu; R. Isocrate; X. Jiang; F. Li; I. Lippi; F. Marini; Z. Ning; A. Olshevskiy; D. Pedretti; P.A. Petitjean; M. Robens; V. Shutov; A. Stahl; J. Steinmann; Y. Sun; S. van Waasen; Y. Wang; Z. Wang; W. Wei; X. Yan; Y. Yang; A. Aiello; A. Andronico; V. Antonelli; W. Bandini; A. Brigatti; A. Barresi; A. Budano; R. Bruno; A. Cabrera; A. Cammi; R. Caruso; D. Chiesa; C. Clementi; S. Costa; X. Ding; S. Dusini; A. Fabbri; M. Fargetta; G. Fiorentini; R. Ford; A. Formozov; M. Giammarchi; M. Grassi; C. Landini; P. Lombardi; C. Lombardo; Y. Malyshkin; F. Mantovani; S.M. Mari; C. Martellini; A. Martini; E. Meroni; M. Mezzetto; L. Miramonti; P. Montini; M. Montuschi; M. Nastasi; F. Ortica; A. Paoloni; S. Parmeggiano; N. Pelliccia; E. Previtali; G. Ranucci; D. Riondino; A.C. Re; B. Ricci; A. Romani; P. Saggese; G. Salamanna; F.H. Sawy; A. Serafini; G. Settanta; C. Sirignano; M. Sisti; L. Stanco; V. Strati; C. Tuvé; G. Verde; L. Votano; J. Zhang. 2020. "Embedded readout electronics R&D for the large PMTs in the JUNO experiment." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 985, no. : 164600.

Journal article
Published: 26 June 2020 in The European Physical Journal Plus
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ACS Style

Christian Castagna; Eric Cervi; Stefano Lorenzi; Antonio Cammi; Davide Chiesa; Monica Sisti; Massimiliano Nastasi; Ezio Previtali. Erratum to: A Serpent/OpenFOAM coupling for 3D burnup analysis. The European Physical Journal Plus 2020, 135, 1 .

AMA Style

Christian Castagna, Eric Cervi, Stefano Lorenzi, Antonio Cammi, Davide Chiesa, Monica Sisti, Massimiliano Nastasi, Ezio Previtali. Erratum to: A Serpent/OpenFOAM coupling for 3D burnup analysis. The European Physical Journal Plus. 2020; 135 (6):1.

Chicago/Turabian Style

Christian Castagna; Eric Cervi; Stefano Lorenzi; Antonio Cammi; Davide Chiesa; Monica Sisti; Massimiliano Nastasi; Ezio Previtali. 2020. "Erratum to: A Serpent/OpenFOAM coupling for 3D burnup analysis." The European Physical Journal Plus 135, no. 6: 1.

Journal article
Published: 11 June 2020 in Annals of Nuclear Energy
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In this work, non-modal stability theory is used to study the non-linear dynamics of the Pressurised Water Reactor (PWR), using a zero-dimensional model. Usually, stability analysis for nuclear reactors is performed using modal methods. Instead, the non-modal approach used in the present work offers a different perspective. This approach considers the so-called short-term behaviour following a disturbance instead of the asymptotic (long-term) one. In the model, point-reactor kinetics with six groups delayed neutrons is used for neutronics, whereas thermal-hydraulics is treated using a two-region model (fuel and coolant). The non-orthogonality of the dynamic matrix of the obtained system shows the possibility of transient energy growth following a disturbance, and the proposed stability analysis offers proof of this. A sensitivity analysis of some parameters is then carried out to study how their variation influences the short-term response of the system. The results of this analysis allow for a ranking of the parameters, allowing the identification of the most significant ones regarding system stability.

ACS Style

Carolina Introini; Antonio Cammi; Francesca Giacobbo. Stability analysis of a zero-dimensional model of PWR core using non-modal stability theory. Annals of Nuclear Energy 2020, 146, 107624 .

AMA Style

Carolina Introini, Antonio Cammi, Francesca Giacobbo. Stability analysis of a zero-dimensional model of PWR core using non-modal stability theory. Annals of Nuclear Energy. 2020; 146 ():107624.

Chicago/Turabian Style

Carolina Introini; Antonio Cammi; Francesca Giacobbo. 2020. "Stability analysis of a zero-dimensional model of PWR core using non-modal stability theory." Annals of Nuclear Energy 146, no. : 107624.

Regular article
Published: 19 May 2020 in The European Physical Journal Plus
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Molten salt reactors (MSRs) have gained worldwide interest in recent years due to their appealing safety and resource utilisation characteristics. These reactors have a unique feature, i.e. the presence of nuclear fuel in the form of a molten fluoride or chloride salt containing the fissile and fertile materials. The fuel salt also acts as the coolant, and this dual role results in a complex, highly coupled multiphysics system which poses a challenge in modelling and simulation of MSRs. This paper presents the development of a simulation model for the Molten Salt Fast Reactor (MSFR) to predict the behaviour of inert gas bubbles in the core and to quantify their impact on the reactivity. Inert gas bubbles in MSFR have been modelled using a multiphysics approach coupling computational fluid dynamics for fluid flow and heat transfer with neutron diffusion equation for neutronics and a balance equation with diffusion and advection terms for taking into account the drift of the delayed neutron precursors. The two-phase flow has been modelled using a simplified Euler–Euler model for small volume fraction of the dispersed phase, i.e. for small bubble fraction, which combines the momentum and continuity equation of the liquid and gas phases and adds a gas-phase transport equation to track the void fraction. Simulations reveal that the bubble distribution in the core has a significant impact on reactivity resulting in a difference in the bubbling feedback coefficient compared to studies using a homogeneous distribution.

ACS Style

Parikshit Bajpai; Stefano Lorenzi; Antonio Cammi. A multiphysics model for analysis of inert gas bubbles in Molten Salt Fast Reactor. The European Physical Journal Plus 2020, 135, 1 -22.

AMA Style

Parikshit Bajpai, Stefano Lorenzi, Antonio Cammi. A multiphysics model for analysis of inert gas bubbles in Molten Salt Fast Reactor. The European Physical Journal Plus. 2020; 135 (5):1-22.

Chicago/Turabian Style

Parikshit Bajpai; Stefano Lorenzi; Antonio Cammi. 2020. "A multiphysics model for analysis of inert gas bubbles in Molten Salt Fast Reactor." The European Physical Journal Plus 135, no. 5: 1-22.

Regular article
Published: 01 May 2020 in The European Physical Journal Plus
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In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuclear systems through the coupling between neutronics and thermal hydraulics. Indeed, a multi-physics approach improves the reactor safety analysis and the design of different types of nuclear systems; in addition, it allows the investigation of physical effects at different scales of time and space. In this context, a challenging task is the development of multi-physics tools to study the fuel cycle. This paper presents a modelling approach for 3D burnup analysis with the Serpent Monte Carlo code that implements an external interface for the coupling with OpenFOAM, importing material temperatures and density field. We adopt CFD to simulate thermal hydraulics for its high flexibility that simplifies the management of input data. In addition, the coupling with a Monte Carlo code assures a natural description of the different physics phenomena of nuclear reactors. We carry out the burnup calculations for one year of burnup of a PWR fuel cell, composed of an \(\hbox {UO}_{2}\) pin surrounded by water. We compare the results to those obtained from simulations that adopt uniform temperature and density distributions. The results show that thermal hydraulics feedback influences the spatial distribution of the reaction rates over the time, leading to a remarkable effect on the nuclide density field along the radial and axial direction. In future works, we plan to extend the analysis for fuel assembly design.

ACS Style

Christian Castagna; Eric Cervi; Stefano Lorenzi; Antonio Cammi; Davide Chiesa; Monica Sisti; Massimiliano Nastasi; Ezio Previtali. A Serpent/OpenFOAM coupling for 3D burnup analysis. The European Physical Journal Plus 2020, 135, 1 -20.

AMA Style

Christian Castagna, Eric Cervi, Stefano Lorenzi, Antonio Cammi, Davide Chiesa, Monica Sisti, Massimiliano Nastasi, Ezio Previtali. A Serpent/OpenFOAM coupling for 3D burnup analysis. The European Physical Journal Plus. 2020; 135 (5):1-20.

Chicago/Turabian Style

Christian Castagna; Eric Cervi; Stefano Lorenzi; Antonio Cammi; Davide Chiesa; Monica Sisti; Massimiliano Nastasi; Ezio Previtali. 2020. "A Serpent/OpenFOAM coupling for 3D burnup analysis." The European Physical Journal Plus 135, no. 5: 1-20.

Journal article
Published: 24 March 2020 in The European Physical Journal Plus
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A new method of Serpent–OpenFOAM coupling is developed as a multi-physics model for Advanced Lead Fast Reactor Demonstrator. The reactor core is simulated in Serpent, a continuous-energy Monte Carlo reactor physics code for neutronic analysis. A three-dimensional geometry is modeled for the calculation of neutronic parameters of the reactor initial core operation. The calculated parameters are evaluated with a good agreement compared to the available reference. The fuel assembly with the maximum power is pinpointed in order to be used for thermal-hydraulic analysis. A thermal-hydraulic model is developed to perform computational fluid dynamics calculation using OpenFOAM software, with an application of a heat conjugate transfer solver written in C++ language. A symmetric one-six of the fuel assembly with the highest power is considered in order to reduce the time of calculation. A multi-physics approach is adopted to map Serpent and OpenFOAM coupling for neutronic and thermal-hydraulic analysis. Moreover, a procedure is implemented in order to evaluate the convergence while coupling Serpent and OpenFOAM. With the implementation of multi-physics model, the maximum temperature of the fuel and coolant is investigated in order to observe any malfunctions. The results show that the coolant and the fuel temperature limits for the ALFRED’s initial core are well preserved for the fuel assembly with the highest power.

ACS Style

Mostafa Jamalipour; Antonio Cammi; Stefano Lorenzi. A coupled neutronic and thermal-hydraulic model for ALFRED. The European Physical Journal Plus 2020, 135, 1 -23.

AMA Style

Mostafa Jamalipour, Antonio Cammi, Stefano Lorenzi. A coupled neutronic and thermal-hydraulic model for ALFRED. The European Physical Journal Plus. 2020; 135 (3):1-23.

Chicago/Turabian Style

Mostafa Jamalipour; Antonio Cammi; Stefano Lorenzi. 2020. "A coupled neutronic and thermal-hydraulic model for ALFRED." The European Physical Journal Plus 135, no. 3: 1-23.

Journal article
Published: 27 February 2020 in Fusion Engineering and Design
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The in-box LOCA (Loss of Coolant Accident) is a relevant safety issue for the design of the WCLL BB. Research activities are ongoing to master phenomena and processes occurring during the postulated accident, to enhance the predictive capability and reliability of numerical tools, and to validate computer models, codes and procedures for their applications. Current status of knowledge requires the availability of qualified and reliable experimental data to support these activities. In view of this, the new separate effect test facility LIFUS5/Mod3 has been commissioned and the Series D experimental campaign is in progress. The tests are focused on the generation of reliable experimental data for the validation of the modified version SIMMER codes for fusion application. Moreover, data will be also used to investigate the dynamic effects of energy release on the structures and to provide relevant feedbacks for the follow up experimental campaigns. The experimental data and results of Test D1.1 are reported and critically discussed, focusing on pressures, temperatures, amount of injected water, and hydrogen production quantification.

ACS Style

Marica Eboli; Riccardo Maria Crugnola; Antonio Cammi; Samad Khani; Nicola Forgione; Alessandro Del Nevo. Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility. Fusion Engineering and Design 2020, 156, 111582 .

AMA Style

Marica Eboli, Riccardo Maria Crugnola, Antonio Cammi, Samad Khani, Nicola Forgione, Alessandro Del Nevo. Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility. Fusion Engineering and Design. 2020; 156 ():111582.

Chicago/Turabian Style

Marica Eboli; Riccardo Maria Crugnola; Antonio Cammi; Samad Khani; Nicola Forgione; Alessandro Del Nevo. 2020. "Test Series D experimental results for SIMMER code validation of WCLL BB in-box LOCA in LIFUS5/Mod3 facility." Fusion Engineering and Design 156, no. : 111582.