F. D'Auria

发表

Thermal-hydraulic phenomena for water cooled nuclear reactors

N. Aksan, F. D'Auria, H. Glaeser, 2018 .

Verification of TRANSURANUS Code Versions v1m1j07 and v1m1j08 against BWR Inter-Ramp Experiments

Lelio Luzzi, F. D'Auria, A. Del Nevo, 2008 .

Application of coupled code technique to a safety analysis of a standard MTR research reactor

Anis Bousbia-Salah, Tewfik Hamidouche, El Khider Si-Ahmed, 2009 .

Investigation of accident management procedures related to loss of feedwater and station blackout in PSB-VVER integral test facility

F. D'Auria, A. Del Nevo, Oleg I. Melikhov, 2012 .

"Post-test analysis of LOBI experiment BL-21 by RELAP5/MOD2 code", 9th Meet. of LOBI LPTF, Ispra (I), Sept. 26-28, 1988

G. M. Galassi, F. D'Auria, 1988 .

Capabilities of System Codes in Simulating Small Break LOCAs in PWRs

G. M. Galassi, Francesco Oriolo, F. D'Auria, 1986 .

The BEPU Challenge in Current Licensing of Nuclear Reactors

Alessandro Petruzzi, Oscar Mazzantini, F. D'Auria, 2010 .

PIPER-ONE research: facility description for OECD-CSNI International Standard Problem N. 21 (ISP 21)

F. D'Auria, C. Billa, P. Vigni, 1986 .

IAEA SPE-1: pre-test calculation of a SBLOCA in the Hungarian PMK-NVH experimental facility performed at Pisa University by RELAP4/MOD6 and RELAP5/MOD1-EUR computer codes

G. M. Galassi, F. D'Auria, G. De Toma, 1986 .

Evaluation of the data base from computer codes calculations of small break LOCA counterpart tests performed in LOBI, SPES, BETHSY and LSTF facilities

G. M. Galassi, F. D'Auria, S Belsito, 1993 .

Uncertainty and Sensitivity Analysis for a Nuclear Power Plant Large Break Loss of Coolant Accident (LB-LOCA) in the Context of OECD BEMUSE Programme

Francesc Reventos, H. Glaeser, F. D'Auria, 2011 .

FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics

A. Kovtonyuk, Alessandro Petruzzi, D. Bestion, 2015 .

Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE programme

Francesc Reventos, R. Meca, A. de Crécy, 2008 .

"Post-test analysis of International Standard Problem 25 by Relap5/mod3 code" (in Italian)

Francesco Oriolo, G. Fruttuoso, F. D'Auria, 1990 .

OECD CSNI ISP 15: pre-test analysis of a split break transient in FIX-II loop performed at Pisa University by RELAP4/MOD6 code

G. M. Galassi, F. D'Auria, 1983 .

Specialists Meeting on Small Break LOCA Analyses in LWRs

F. D'Auria, P. Vigni, Marino Mazzini, 1985 .

Application of Cathare code to the analysis of Pactel experiments relevant to innovative reactors

G. M. Galassi, F. D'Auria, M Frogheri, 1999 .

Evaluation of Code accuracy in the prediction of OECD/CSNI ISP 22, OECD CSNI Final Workshop on ISP 22 - Pisa (I) July 2-4 1991

Walter Ambrosini, F. D'Auria, Breghi Maria Paola, 1991 .

International Training Program in Support of Safety Analysis: 3D S.UN.COP — Scaling, Uncertainty and 3D Thermalhydraulics/Neutron-Kinetics Coupled Codes Seminar

Francesc Reventos, A. Kovtonyuk, Alessandro Petruzzi, 2012 .

Thermal-hydraulic phenomena and code requirements for future reactors safety analysis

G. M. Galassi, Francesco Oriolo, F. D'Auria, 1992 .

Statistical Evaluation of a Thermalhydraulic Data Base

G. M. Galassi, F. D'Auria, F Sugaroni, 1994 .

Uncertainty and sensitivity analysis of a LBLOCA in a PWR Nuclear Power Plant: Results of the Phase V of the BEMUSE programme

Francesc Reventos, A. de Crécy, P. Bazin, 2011 .

Preservation and Use of Integral System Test Facilities Data: the Experience of the Lobi Data and the Stresa Database

G. M. Galassi, F. D'Auria, P Pla, 2012 .

Application of the Cathare 2 v1.3U code to the analysis of the Pactel GDE-24 experiment relevant to the innovative reactors, EU Meeting, Lappeenranta (SF), March 14, 1997

G. M. Galassi, F. D'Auria, Monica Frogheri, 1997 .

User and Models Interactions in System Codes Predictions

F. D'Auria, G. M Galassi, P Lombardi, 1990 .

LOBI test B-302: electric power evaluation and pre-test analysis performed by RELAP4/MOD6 computer code", University of Pisa Report, DCMN - RP 002(82), Pisa (I)

M. Mazzini, Francesco Oriolo, F. D'Auria, 1982 .

Applications of SYS TH codes to nuclear reactor design and accident analysis

G. M. Galassi, F. D'Auria, 2017 .

Coupling of CFD and SYS TH codes in BEPU approach, Case study : two-phase PTS scenario

F. D'Auria, Mohammad B. Ghofrani, M. Ghafari, 2017 .

Challenges and concerns for development of nuclear thermal-hydraulics

F. D'Auria, Y. Hassan, Y. Hassan, 2021 .

More than 30 years of Reactor Thermalhydraulics

F. D'Auria, A. B. Wahba, 1998 .

Small modular reactor full scope core optimization using Cuckoo Optimization Algorithm

F. D'Auria, R. Akbari, D. Rezaei Ochbelagh, 2020 .

BEMUSE Programme. Phase 2 report

Francesc Reventos, M. Kyncl, P. Bazin, 2006 .

Relap5/mod3.2 post-test analysis and accuracy quantification of LSTF test SB-CL-21

G. M. Galassi, F. D'Auria, Velamir Segon, 1998 .

On the convergence of Relap5 calculations in a single-phase natural circulation test problem

Walter Ambrosini, J. C. Ferreri, F. D'Auria, 1995 .

US NRC NUREG - RELAP5/MOD3.2 Post Test Analysis and Accuracy Quantification of SPES Test SP-SB-03

F. D'Auria, Frogheri Monica, Giannotti Walter, 1999 .

A novel methodology of internal assessment of uncertainty for coupled three-dimensional neutronics thermal-hydraulics system codes

Alessandro Petruzzi, Kostadin Ivanov, F. D'Auria, 2003 .

UMAE Application: Contribution to the OECD/CSNI UMS vol. 2

G. M. Galassi, F. D'Auria, S Belsito, 1997 .

Preliminary Review of Selected Chapters of the Final Safety Analysis Report (FSAR) for Bushehr NPP, Unit 1: Chapter 15 – Accident Analysis. IAEA TC Project IRA 4035 Task 7.2

F. D'Auria, F. D'Auria, N Tricot, 2008 .

Introduction to Nuclear Reactor Thermalhydraulics", Lecture L2 at Course on Thermal-hydraulic Phenomena in Nuclear Reactor Technology

F. D'Auria, 1987 .

Core Exit Temperature Effectiveness in Accident Management of Nuclear Power Reactor

A. Del Nevo, F. D'Auria, Marco Cherubini, 2010 .

Notes to the results obtained by DCMN of Pisa University in the participation to the NEA-OECD BWR Benchmark, OECD-NEA Workshop on BWR Benchmark, Paris (F) May 10-12, 1995

G. M. Galassi, Walter Ambrosini, F. D'Auria, 1995 .

PIPER-ONE research: boundary and initial conditions for OECD-CSNI International Standard Problem 21 (ISP 21)

G. M. Galassi, F. D'Auria, Marino Mazzini, 1986 .

The three-dimensional neutron kinetics coupled with thermal-hydraulics in RBMK accident analysis

Kostadin Ivanov, Carlo Parisi, F. D'Auria, 2008 .

Flowrate and density oscillations during two-phase natural circulation in PWR typical conditions

G. M. Galassi, F. D'Auria, 1990 .

Semi 2D modeling of the horizontal steam generator PGV-1000 using the RELAP5 code

F. D'Auria, Gholamreza Jahanfarnia, Ehsan Zarifi, 2009 .

RELAP5/MOD3 .2 Post Test Analysis and Accuracy Quantification of SPES Test SP-SB-04

F. D'Auria, Frogheri Monica, Giannotti Walter, 1999 .