| Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects M Brovchenko, JL Kloosterman, L Luzzi, E Merle, D Heuer, A Laureau, ... EPJ N-Nuclear Sciences & Technologies 5, 2, 2019 | 61 | 2019 |
| Optimization of the pre-conceptual design of the MSFR M Brovchenko, E Merle Lucotte, H Rouch, F Alcaro, M Allibert, M Aufiero, ... | 32 | 2013 |
| Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool O Coindreau, B Jäckel, F Rocchi, F Alcaro, D Angelova, G Bandini, ... Annals of Nuclear Energy 120, 880-887, 2018 | 27 | 2018 |
| BEPU analysis of a passive decay heat removal system with RELAP5/MOD3. 3 and RELAP5-3D F Alcaro, A Bersano, C Bertani, F Mascari Progress in Nuclear Energy 136, 103724, 2021 | 18 | 2021 |
| System codes benchmarking on a low sodium void effect SFR heterogeneous core under ULOF conditions E Bubelis, A Tosello, W Pfrang, M Schikorr, K Mikityuk, AL Panadero, ... Nuclear Engineering and Design 320, 325-345, 2017 | 17 | 2017 |
| Multiscale modelling of the phénix dissymmetric test benchmark HJ Uitslag-Doolaard, F Alcaro, F Roelofs, X Wang, A Kraus, A Brunett, ... Nuclear Engineering and Design 356, 110375, 2020 | 16 | 2020 |
| System thermal-hydraulic modelling of the phénix dissymmetric test benchmark V Narcisi, F Giannetti, A Del Nevo, F Alcaro, X Wang, A Kraus, A Brunett, ... Nuclear Engineering and Design 353, 110272, 2019 | 11 | 2019 |
| Optimization of the preconceptual design of the MSFR-Evaluation and Viability of Liquid Fuel Fast Reactor System EVOL M Brovchenko, E Merle-Lucotte, H Rouch, F Alcaro, M Allibert, M Aufiero, ... Technical report, CNRS/IN2P3/LPSC et al, September, 2013 | 9 | 2013 |
| Implementation of the quasi-static method for neutron transport F Alcaro, S Dulla, P Ravetto, R Le Tellier, C Suteau | 7 | 2011 |
| Development of dynamic models for neutron transport calculations F Alcaro, S Dulla, G Marleau, EH Mund, P Ravetto Il Nuovo cimento della Società italiana di fisica. C 33 (1), 13, 2010 | 7 | 2010 |
| Validation of Thermal Hydraulic Design Support and Safety Methodology and Application Sealer F Roelofs, K Zwijsen, H Uitslag-Doolaard, F Alcaro, M Stempniewicz, ... | 5 | 2021 |
| Numerical simulations at different scales for the CIRCE facility K Zwijsen, D Dovizio, P Breijder, F Alcaro, F Roelofs ICAPP, 935-944, 2018 | 5 | 2018 |
| System thermal hydraulics and multiscale simulations of the dissymmetric transient in the Phenix reactor HJ Uitslag-Doolaard, F Alcaro, F Roelofs, K Zwijsen ICAPP, 2018 | 3 | 2018 |
| MELCOR modeling and experience at NRG F Alcaro European MELCOR Group User Group, EMUG Meeting, Boston, USA, 2015 | 3 | 2015 |
| OECD/NEA/CSNI/WGAMA PERSEO benchmark: main outcomes and conclusions F Mascari, A Bersano, F Alcaro, M Stempniewicz, L Albright, T Jevremovic, ... Nuclear Engineering and Design 405, 112220, 2023 | 2 | 2023 |
| SFP-LOCA Analysis with MELCOR F Alcaro, MM Stempniewicz 8th meeting of the European MELCOR User Group, London, UK, 2016 | 2 | 2016 |
| Neutronic evaluations for the EVOL molten salt reactor F Alcaro, S Dulla, P Ravetto Transactions of the American Nuclear Society 108, 927-930, 2013 | 2 | 2013 |
| Results of the PHENIX dissymmetric test benchmark exercise C Geffray, HJ Uitslag-Doolaard, A Gerschenfeld, F Alcaro, A Kraus, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2019 | 1 | 2019 |
| Development of a model for core dynamics-Neutronics S Dulla, P Ravetto, S Han, F Alcaro CERSE-UNIBO RL 1258, 2010 | 1 | 2010 |
| Alternative factorization methods for reactor kinetics S Dulla, F Alcaro, P Ravetto Transactions of the American Nuclear Society 103, 718-720, 2010 | 1 | 2010 |
