Francesco D'auria
Francesco D'auria
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Cited by
Outline of the uncertainty methodology based on accuracy extrapolation
F D’auria, N Debrecin, GM Galassi
Nuclear technology 109 (1), 21-38, 1995
Development of a code with the capability of internal assessment of uncertainty
F D’Auria, W Giannotti
Nuclear technology 131 (2), 159-196, 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
Thermal-hydraulic system codes in nulcear reactor safety and qualification procedures
A Petruzzi, F D'Auria
Science and Technology of Nuclear Installations 2008, 2008
Code validation and uncertainties in system thermalhydraulics
F D'auria, GM Galassi
Progress in Nuclear Energy 33 (1-2), 175-216, 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
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
Evaluation of accuracy of thermal hydraulic code calculation
W Ambrosini, R Bovalini
Energia Nucleare (Rome) 7 (2), 5-16, 1990
Methodology for the qualification of thermal-hydraulic codes nodalization
M Bonuccelli, F D'auria, N Debrecin, GM Galassi
International Topical Meeting on Nuclear Reactor Thermal-hydraulics (NURETH-6) 1, 1993
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
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
Scaling in nuclear reactor system thermal-hydraulics
F D’Auria, GM Galassi
Nuclear Engineering and Design 240 (10), 3267-3293, 2010
State of the art in using best estimate calculation tools in nuclear technology
F D'auria, BS ANIS, A Petruzzi, AD Nevo
Nuclear Engineering and Technology 38 (1), 11-32, 2006
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
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
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
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
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
A separate effects test matrix for thermal-hydraulic code validation: phenomena characterization and selection of facilities and tests
N Aksan, F D’auria, H Glaeser, R Pochard, C Richards, A Sjoberg
OECD0GD 94, 82, 1993
An overview of the pressurized thermal shock issue in the context of the NURESIM project
D Lucas, D Bestion, E Bodèle, P Coste, M Scheuerer, F D'Auria, ...
Science and Technology of Nuclear Installations 2009, 2008
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