Francesco Saverio D'Auria

Author

University of Pisa ORCID

Also Known As

F. D'Auria, F. D’Auria, Francesco D'AURIA, Francesco D'Auria, Francesco D’Auria, Francesco Saverio D'Auria

204

Publications

794

Citations

H-Index

Concepts

All Affiliations

University of Pisa Orano (France)Gidropribor Joint Research Centre University of Genoa

About

Francesco Saverio D'Auria is an author at University of Pisa specializing in engineering, modeling and simulation, and systems engineering.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	14	20	546
2	Civil Engineering	5	5	108
3	Education	1	1	33
4	Computer Engineering	1	1	15
5	Computer Science	1	1	88

Francesco Saverio D'Auria

Publications

538

Citations

H-Index

Page 1

	Year	Citations
Transient and stability analysis in single-phase natural circulation Seyed Khalil Mousavian, Mario Misale, Francesco Saverio D'Auria, Annals of Nuclear Energy Two-phase FlowEngineeringFluid MechanicsNatural CirculationNatural Convection	2004	108
Code validation and uncertainties in system thermalhydraulics Francesco Saverio D'Auria, G. M. Galassi Progress in Nuclear Energy EngineeringCalibrationVerificationSystems EngineeringCode Validation	1998	88
CSNI Code Validation Matrix of Thermo-Hydraulic Codes for LWR LOCA and Transients S.R. Aksan, D. Bessette, I. Brittain, EngineeringLwr LocaThermal HydraulicsCivil EngineeringThermo-hydraulic Codes	1987	35
Methodology for the Evaluation of Thermalhydraulic Codes Accuracy Francesco Saverio D'Auria, Michele Leonardi, R. Pochard CINECA IRIS Institutial research information system (University of Pisa) EngineeringMeasurementCalibrationTemperature MeasurementEducation	1994	33
State of the Art Report on Boiling Water Reactor Stability (SOAR ON BWRS) Francesco Saverio D'Auria, Walter Ambrosini, Takafumi Anegawa, CINECA IRIS Institutial research information system (University of Pisa) EngineeringReactor DesignNuclear ReactorsNuclear Reactor EngineeringNuclear Safety	1997	26
PREMIUM, a benchmark on the quantification of the uncertainty of the physical models in the system thermal-hydraulic codes: methodologies and data review F. Reventós, A. de Alfonso, Rafael Mendizábal, Thermodynamic ModellingEngineeringThermal HydraulicsUncertainty QuantificationCivil Engineering	2016	26
Simulation of an hypothetical out-of-phase instability case in boiling water reactor by RELAP5/PARCS coupled codes Antonella Lombardi Costa, Cláubia Pereira, Walter Ambrosini, Annals of Nuclear Energy EngineeringNumerical SimulationWater ReactorModeling And SimulationThermodynamics	2007	24
User Effects on the Thermalhydraulic Transient System Codes Calculations S.N. Aksan, Francesco Saverio D'Auria, H. Staedtke Nuclear Engineering and Design Thermodynamic ModellingEngineeringUser EffectsSystems EngineeringThermal Analysis	1993	22
Two-Phase Critical Flow Models Francesco Saverio D'Auria, P. Vigni CINECA IRIS Institutial research information system (University of Pisa) EngineeringPhase EquilibriumNumerical SimulationModeling And SimulationMultiphase Flow	1980	21
FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics Seung-Hoon Ahn, N. Aksan, H. Austregesilo, Nuclear Engineering and Design Thermodynamic ModellingSystem Thermal-hydraulic CodesCore Thermal HydraulicsEngineeringNuclear Reactor Thermal-hydraulics	2014	20

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