| Sensitivity analysis of the MASLWR helical coil steam generator using TRACE F Mascari, G Vella, BG Woods, K Welter, J Pottorf, E Young, M Adorni, ... Nuclear Engineering and Design 241 (4), 1137-1144, 2011 | 37 | 2011 |
| Sensitivity Analysis of the MASLWR Helical Coil Steam Generator Using TRACE F Mascari, G Vella, B Woods, K Welter, J Pottorf, E Young, M Adorni, ... International Conference Nuclear Energy for New Europe 2009, Bled, Slovenia …, 2009 | 37 | 2009 |
| Scaling Issues for the Experimental Characterization of Reactor Coolant System in Integral Test Facilities and Role of System Code as Extrapolation Tool F Mascari, H Nakamura, K Umminger, F De Rosa, F D'Auria Proceedings of the 16th International Topical Meeting on Nuclear Reactor …, 2015 | 36 | 2015 |
| The EC MUSA project on management and uncertainty of severe accidents: main pillars and status LE Herranz, S Beck, VH Sánchez-Espinoza, F Mascari, S Brumm, ... Energies 14 (15), 4473, 2021 | 35 | 2021 |
| Analyses of the OSU‐MASLWR Experimental Test Facility F Mascari, G Vella, BG Woods, F D′ Auria Science and Technology of Nuclear Installations 2012 (1), 528241, 2012 | 33 | 2012 |
| A Bayesian framework of inverse uncertainty quantification with principal component analysis and Kriging for the reliability analysis of passive safety systems G Roma, F Di Maio, A Bersano, N Pedroni, C Bertani, F Mascari, E Zio Nuclear Engineering and Design 379, 111230, 2021 | 24 | 2021 |
| Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis A Bersano, F Mascari, MT Porfiri, P Maccari, C Bertani Fusion Engineering and Design 159, 111944, 2020 | 24 | 2020 |
| International Agreement Report – Analysis of the OSU-MASLWR 001 and 002 Tests by Using the TRACE Code (NUREG/IA-0466) F Mascari, F De Rosa, BG Woods, K Welter, G Vella, F D'Auria NUREG/IA-0466, 2016 | 17* | 2016 |
| 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 | 16 | 2021 |
| Progress in modeling in-containment source term with ASTEC-Na LE Herranz, L Lebel, F Mascari, C Spengler Annals of Nuclear Energy 112, 84-93, 2018 | 15 | 2018 |
| Analysis of unmitigated large break loss of coolant accidents using MELCOR code M Pescarini, F Mascari, D Mostacci, F De Rosa, C Lombardo, F Giannetti 35th Heat Transfer Conference, Ancona, Italy June 26-28, 2017, 2017 | 14 | 2017 |
| Analysis of primary/containment coupling phenomena characterizing the MASLWR design during a SBLOCA scenario F Mascari, G Vella, BG Woods, K Welter, F D’Auria Nuclear Power Plants, 2012 | 14 | 2012 |
| TRACE, RELAP5 Mod 3.3, and RELAP5-3D code comparison of OSU-MASLWR-001 test J Pottorf, F Mascari, BG Woods Transactions of the American Nuclear Society 101, 2009 | 13 | 2009 |
| Modelling flow and heat transfer in helically coiled pipes F Castiglia, P Chiovaro, M Ciofalo, M Di Liberto, PA Di Maio, I Di Piazza, ... Cirten-Unipa RL-1205, University of Palermo, Palermo, Italy, 2010 | 12 | 2010 |
| Analysis, by TRACE code, of Natural Circulation Phenomena in the MASLWR-OSU-002 Test F Mascari, BG Woods, M Adorni Proceedings of the International Conference Nuclear Energy for New Europe 2008, 2008 | 11 | 2008 |
| Passive safety systems analysis: A novel approach for inverse uncertainty quantification based on Stacked Sparse Autoencoders and Kriging metamodeling G Roma, F Antonello, F Di Maio, N Pedroni, E Zio, A Bersano, C Bertani, ... Progress in Nuclear Energy 148, 104209, 2022 | 10 | 2022 |
| FASTNET scenarios database development and status F Mascari, F Rocchi, P Carny, L Liptak, M Adorni, J Fontanet, LE Herranz, ... submitted to ERMSAR, 2019 | 10 | 2019 |
| TRACE code analyses for the IAEA ICSP on “Integral PWR design natural circulation flow stability and thermo-hydraulic coupling of containment and primary system during accidents” F Mascari, G Vella, BG Woods ASME 2011 Small Modular Reactors Symposium, 257-267, 2011 | 10 | 2011 |
| Plan for an IAEA International Collaborative Standard Problem on Integral PWR Design Natural Circulation Flow Stability and Thermo-Hydraulic Coupling of Containment and Primary … BG Woods, F Mascari Department of Nuclear Engineering and Radiation Health Physics, Oregon State …, 2009 | 10 | 2009 |
| ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR P Maccari, F Mascari, S Ederli, P Meloni, S Manservisi Annals of Nuclear Energy 156, 108194, 2021 | 9 | 2021 |
Fabio Giannetti"Sapienza" University of Rome在 uniroma1.it 的电子邮件经过验证
