| POD-Galerkin method for finite volume approximation of Navier–Stokes and RANS equations S Lorenzi, A Cammi, L Luzzi, G Rozza Computer Methods in Applied Mechanics and Engineering 311, 151-179, 2016 | 166 | 2016 |
| POD-Galerkin reduced order methods for CFD using Finite Volume Discretisation: vortex shedding around a circular cylinder G Stabile, S Hijazi, A Mola, S Lorenzi, G Rozza Communications in Applied and Industrial Mathematics 8 (1), 210-236, 2017 | 155 | 2017 |
| Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor E Cervi, S Lorenzi, A Cammi, L Luzzi Chemical Engineering Science 193, 379-393, 2019 | 69 | 2019 |
| Object-oriented modelling and simulation for the ALFRED dynamics R Ponciroli, A Bigoni, A Cammi, S Lorenzi, L Luzzi Progress in Nuclear Energy 71, 15-29, 2014 | 53 | 2014 |
| Results from a multi-physics numerical benchmark for codes dedicated to molten salt fast reactors M Tiberga, RGG de Oliveira, E Cervi, JA Blanco, S Lorenzi, M Aufiero, ... Annals of Nuclear Energy 142, 107428, 2020 | 52 | 2020 |
| A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants W Wang, A Cammi, F Di Maio, S Lorenzi, E Zio Reliability Engineering & System Safety 175, 24-37, 2018 | 52 | 2018 |
| Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor L Luzzi, A Cammi, V Di Marcello, S Lorenzi, D Pizzocri, P Van Uffelen Nuclear Engineering and Design 277, 173-187, 2014 | 46 | 2014 |
| Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches E Cervi, S Lorenzi, L Luzzi, A Cammi Annals of Nuclear Energy 132, 227-235, 2019 | 43 | 2019 |
| Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor E Cervi, S Lorenzi, A Cammi, L Luzzi Nuclear Engineering and Design 346, 209-219, 2019 | 43 | 2019 |
| On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives C Fiorina, I Clifford, S Kelm, S Lorenzi Nuclear Engineering and Design 387, 111604, 2022 | 42 | 2022 |
| Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor A Di Ronco, A Cammi, S Lorenzi Nuclear Engineering and Technology 52 (1), 51-58, 2020 | 38 | 2020 |
| Development of the ALFRED reactor full power mode control system R Ponciroli, A Cammi, A Della Bona, S Lorenzi, L Luzzi Progress in Nuclear Energy 85, 428-440, 2015 | 33 | 2015 |
| A reduced order model for investigating the dynamics of the Gen-IV LFR coolant pool S Lorenzi, A Cammi, L Luzzi, G Rozza Applied Mathematical Modelling 46, 263-284, 2017 | 32 | 2017 |
| Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core A Di Ronco, C Introini, E Cervi, S Lorenzi, YS Jeong, SB Seo, IC Bang, ... Nuclear Engineering and Design 362, 110529, 2020 | 29 | 2020 |
| Development of a reduced order model for fuel burnup analysis C Castagna, M Aufiero, S Lorenzi, G Lomonaco, A Cammi Energies 13 (4), 890, 2020 | 29 | 2020 |
| Reduced order modeling approach for parametrized thermal-hydraulics problems: inclusion of the energy equation in the POD-FV-ROM method L Vergari, A Cammi, S Lorenzi Progress in Nuclear Energy 118, 103071, 2020 | 29 | 2020 |
| An Adjoint Proper Orthogonal Decomposition method for a neutronics reduced order model S Lorenzi Annals of Nuclear Energy 114, 245-258, 2018 | 27 | 2018 |
| Adaptive simulation for failure identification in the advanced lead fast reactor European demonstrator P Turati, A Cammi, S Lorenzi, N Pedroni, E Zio Progress in Nuclear Energy 103, 176-190, 2018 | 24 | 2018 |
| Modeling and analysis of nuclear fuel pin behavior for innovative lead cooled FBR L Luzzi, S Lorenzi, D Pizzocri, D Rozzia, A Aly, A Del Nevo Report RdS/PAR2013/022, 2014 | 24 | 2014 |
| A preliminary approach to the ALFRED reactor control strategy R Ponciroli, A Cammi, S Lorenzi, L Luzzi Progress in Nuclear Energy 73, 113-128, 2014 | 24 | 2014 |
