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A. Petruzzi

Observed names: A Petruzzi, A. PETRUZZI, ALESSANDRO PETRUZZI, Alessandro PETRUZZI, Alessandro Petruzzi, PETRUZZI A, PETRUZZI A., PETRUZZI, ALESSANDRO, Petruzzi A., Petruzzi Alessandro, Petruzzi Alessandro,, Petruzzi, A., Petruzzi, Alessandro
ORCID: 0000-0002-1493-9372
Observed ORCID: 0000-0002-1493-9372
OpenAlex ID: A5039358772
Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures
2008 · Alessandro Petruzzi, Francesco D'Auria · Science and Technology of Nuclear Installations · 117
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Uncertainty and sensitivity analysis of a LBLOCA in a PWR Nuclear Power Plant: Results of the Phase V of the BEMUSE programme
2011 · M. Perez, F. Reventos, et al. · Nuclear Engineering and Design · 87
Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE programme
2008 · A. de Crécy, P. Bazin, et al. · Nuclear Engineering and Design · 74
State of the Art in Using Best Estimate Calculation Tools in Nuclear Technology
2006 · TAB Francesco DAuriaUniversity of Pisa, A Bousbia Salah, et al. · Nuclear Engineering and Technology · 66
SAPIUM: A Generic Framework for a Practical and Transparent Quantification of Thermal-Hydraulic Code Model Input Uncertainty
2020 · Jean Baccou, Jinzhao Zhang, et al. · Nuclear Science and Engineering · 42
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Development of good practice guidance for quantification of thermal-hydraulic code model input uncertainty
2019 · Jean Baccou, Jinzhao Zhang, et al. · Nuclear Engineering and Design · 42
Progress in international best estimate plus uncertainty analysis methodologies
2021 · Robert P. Martin, Alessandro Petruzzi · Nuclear Engineering and Design · 36
Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark
2019 · Tomasz Skorek, Agnès de Crécy, et al. · Nuclear Engineering and Design · 36
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Best-Estimate Model Calibration and Prediction through Experimental Data Assimilation—II: Application to a Blowdown Benchmark Experiment
2010 · Alessandro Petruzzi, Dan G. Cacuci, et al. · Nuclear Science and Engineering · 30
Comparison between Best-Estimate–Plus–Uncertainty Methods and Conservative Tools for Nuclear Power Plant Licensing
2010 · Andrea Bucalossi, Alessandro Petruzzi, et al. · Nuclear Technology · 29
Approaches, Relevant Topics, and Internal Method for Uncertainty Evaluation in Predictions of Thermal-Hydraulic System Codes
2007 · Alessandro Petruzzi, Francesco D'Auria · Science and Technology of Nuclear Installations · 25
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PREMIUM, a benchmark on the quantification of the uncertainty of the physical models in the system thermal-hydraulic codes: methodologies and data review
2016 · F. Reventós, A. de Alfonso, et al. · 24
Standardized Consolidated Calculated and Reference Experimental Database (SCCRED): A Supporting Tool for V&V and Uncertainty Evaluation of Best-Estimate System Codes for Licensing Applications
2015 · A. Petruzzi, F. D’Auria · Nuclear Science and Engineering · 24
Methodology of Internal Assessment of Uncertainty and Extension to Neutron Kinetics/Thermal-Hydraulics Coupled Codes
2005 · A. Petruzzi, F. D’Auria, et al. · Nuclear Science and Engineering · 23
FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics
2014 · S.H. Ahn, N. Aksan, et al. · Nuclear Engineering and Design · 21
The BEPU Evaluation Model with RELAP5-3D for the Licensing of the Atucha-II NPP
2015 · A. Petruzzi, M. Cherubini, et al. · Nuclear Technology · 20
Deterministic Safety Analysis for Nuclear Power Plants. IAEA Specific Safety Guide
2009 · Francesco Saverio D'Auria, M. Dusic, et al. · CINECA IRIS Institutial research information system (University of Pisa) · 17
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International Course to Support Nuclear Licensing by User Training in the Areas of Scaling, Uncertainty, and 3D Thermal-Hydraulics/Neutron-Kinetics Coupled Codes: 3D S.UN.COP Seminars
2008 · Alessandro Petruzzi, Francesco D'Auria, et al. · Science and Technology of Nuclear Installations · 16
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MTR benchmark static calculations with MCNP5 code
2007 · Anis Bousbia-Salah, Hocine Benkharfia, et al. · Annals of Nuclear Energy · 16
Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled thermal–hydraulic 3D kinetics code
2006 · Anis Bousbia Salah, Soeren Kliem, et al. · Nuclear Engineering and Design · 16
Application of SAPIUM Guidelines to Input Uncertainty Quantification: The ATRIUM Project
2023 · A. Ghione, L. Sargentini, et al. · 15
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RELAP5 simulation of surge line break accident using combined and best estimate plus uncertainty approaches
2009 · Marián Krištof, Tomáš Kliment, et al. · Nuclear Engineering and Design · 14
A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity
2024 · J. Baccou, T. Glantz, et al. · Nuclear Engineering and Design · 13
The CASUALIDAD Method for Uncertainty Evaluation of Best-Estimate System Thermal-Hydraulic Calculations
2019 · A. Petruzzi · Nuclear Technology · 13
Nuclear Energy and sustainable Development
2001 · A Bousbia Salah, Antonio Nigro, et al. · 13
Works count: 257
Citation count: 1,134
H-index: 17
I10-index: 32
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