| Outline of the uncertainty methodology based on accuracy extrapolation F D’auria, N Debrecin, GM Galassi Nuclear technology 109 (1), 21-38, 1995 | 245 | 1995 |
| Thermal‐hydraulic system codes in nulcear reactor safety and qualification procedures A Petruzzi, F D′ Auria Science and Technology of Nuclear Installations 2008 (1), 460795, 2008 | 220 | 2008 |
| Development of a code with the capability of internal assessment of uncertainty F D’Auria, W Giannotti Nuclear technology 131 (2), 159-196, 2000 | 203 | 2000 |
| Methodology for the reliability evaluation of a passive system and its integration into a probabilistic safety assessment M Marques, JF Pignatel, P Saignes, F D’auria, L Burgazzi, C Müller, ... Nuclear Engineering and Design 235 (24), 2612-2631, 2005 | 181 | 2005 |
| Code validation and uncertainties in system thermalhydraulics F D'auria, GM Galassi Progress in Nuclear Energy 33 (1-2), 175-216, 1998 | 146 | 1998 |
| Dynamic calculations of the IAEA safety MTR research reactor benchmark problem using RELAP5/3.2 code T Hamidouche, A Bousbia-Salah, M Adorni, F D'Auria Annals of Nuclear Energy 31 (12), 1385-1402, 2004 | 131 | 2004 |
| Transient and stability analysis in single-phase natural circulation SK Mousavian, M Misale, F D'Auria, MA Salehi Annals of Nuclear Energy 31 (10), 1177-1198, 2004 | 125 | 2004 |
| Scaling in nuclear reactor system thermal-hydraulics F D’Auria, GM Galassi Nuclear Engineering and Design 240 (10), 3267-3293, 2010 | 121 | 2010 |
| The Best Estimate Plus Uncertainty (BEPU) approach in licensing of current nuclear reactors F D’Auria, C Camargo, O Mazzantini Nuclear Engineering and Design 248, 317-328, 2012 | 120 | 2012 |
| A methodology for the qualification of thermalhydraulic codes nodalizations M Bonuccelli, FS D'Auria, N Debrecin, GM Galassi 8th Meet. of OECD-CSNI Task Group on Thermalhydraulic System Behaviour, 1992 | 115 | 1992 |
| Reliability evaluation of a natural circulation system J Jafari, F D’Auria, H Kazeminejad, H Davilu Nuclear Engineering and Design 224 (1), 79-104, 2003 | 109 | 2003 |
| Review of quantitative accuracy assessments with fast Fourier transform based method (FFTBM) A Prošek, F D'Auria, B Mavko Nuclear Engineering and Design 217 (1-2), 179-206, 2002 | 102 | 2002 |
| State of the art in using best estimate calculation tools in nuclear technology A BOUSBIA-SALAH, P ALESSANDRO Nuclear engineering and technology 38 (1), 11-32, 2006 | 92 | 2006 |
| Uncertainty and sensitivity analysis of a LBLOCA in a PWR Nuclear Power Plant: Results of the Phase V of the BEMUSE programme M Perez, F Reventos, L Batet, A Guba, I Tóth, T Mieusset, P Bazin, ... Nuclear Engineering and Design 241 (10), 4206-4222, 2011 | 90 | 2011 |
| User effects on the thermal-hydraulic transient system code calculations SN Aksan, F d'Auria, H Staedtke Nuclear Engineering and Design 145 (1-2), 159-174, 1993 | 89 | 1993 |
| Methodology for the evaluation of thermalhydraulic codes accuracy FS D'Auria, M Leonardi, R Pochard Int. Conf. on New Trends in Nuclear System Thermohydraulics, 1994 | 84 | 1994 |
| Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core M Adorni, A Bousbia-Salah, T Hamidouche, B Di Maro, F Pierro, F D’Auria Annals of Nuclear Energy 32 (15), 1679-1692, 2005 | 82 | 2005 |
| Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE programme A de Crécy, P Bazin, H Glaeser, T Skorek, J Joucla, P Probst, K Fujioka, ... Nuclear Engineering and Design 238 (12), 3561-3578, 2008 | 80 | 2008 |
| A model for the analysis of pump start-up transients in Tehran Research Reactor K Farhadi, A Bousbia-Salah, F D'Auria Progress in Nuclear Energy 49 (7), 499-510, 2007 | 76 | 2007 |
| A state-of-the-art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design D Bestion, F D’Auria, P Lien, H Nakamura Nuclear Safety, 2017 | 73* | 2017 |