Fabio Giannetti


Titolo Pubblicato in Anno
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project ANNALS OF NUCLEAR ENERGY 2024
A systematic approach for the adequacy analysis of a set of experimental databases. Application in the framework of the ATRIUM activity NUCLEAR ENGINEERING AND DESIGN 2024
RELAP5/Mod3.3 thermal-hydraulics characterization of the steam generator mock-up during operational transients in STEAM facility in support of the design of the DEMO WCLL BoP FUSION ENGINEERING AND DESIGN 2024
Pre-test analysis of low power operations of STEAM, the EU-DEMO steam generator mock-up facility FUSION ENGINEERING AND DESIGN 2024
Design and integration of the EU-DEMO water-cooled lead lithium breeding blanket ENERGIES 2023
OECD/NEA/CSNI/WGAMA PERSEO benchmark: Main outcomes and conclusions NUCLEAR ENGINEERING AND DESIGN 2023
Conceptual Design of the Steam Generators for the EU DEMO WCLL Reactor ENERGIES 2023
Thermal-hydraulic assessment of Once-Through Steam Generators for EU-DEMO WCLL Breeding Blanket primary cooling system application FUSION ENGINEERING AND DESIGN 2023
Development of a Steam Generator Mock-Up for EU DEMO Fusion Reactor: Conceptual Design and Code Assessment ENERGIES 2023
Subchannel modelling capabilities of RELAP5-3D© for wire-spaced fuel pin bundle NUCLEAR ENGINEERING AND DESIGN 2023
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes ANNALS OF NUCLEAR ENERGY 2023
Thermal-Hydraulic Characterization and Numerical Modeling with RELAP5 Code of ATHENA Secondary Loop NUCLEAR TECHNOLOGY 2023
Analysis and Preliminary Design of Primary Heat Exchanger Failure Testing Facility for Lead-Cooled Fast Reactors NUCLEAR TECHNOLOGY 2023
Transient analysis of SIRIO using RELAP5/MOD3.3 system code JOURNAL OF PHYSICS. CONFERENCE SERIES 2023
The LIFUS5 separate effect test facility experimental programme NUCLEAR ENGINEERING AND DESIGN 2023
ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2023
Dynamic event tree analysis of a severe accident sequence in a boiling water reactor experiencing a cyberattack scenario ANNALS OF NUCLEAR ENERGY 2023
Cutting-edge R&D activities of CIRTEN in support of the Technology Park annexed to the Italian National Repository of radioactive waste IL NUOVO CIMENTO C 2023
Subchannel Analysis of LFR Wire-Wrapped Fuel Bundle with RELAP5-3D NUCLEAR TECHNOLOGY 2023
Estimation of Cesium Penetration Into Concrete Structures After an Experimental Decontamination Activity Conference proceedings - International Conference on Radioactive Waste Management and Environmental Remediation 2023


  • PE8_6


  • Big data & computing
  • Sustainable technologies & development

Interessi di ricerca

The research activity is focused on two-phase thermal-hydraulic transient analysis based on system TH computer programs. He acquired capability mainly in the safety analysis and TH best-estimate transient calculations, with the aid of RELAP5/mod3.3, RELAP5-3D©, TRACE and MELCOR computer programs, to enhance the safety performances and new system/component design for nuclear reactors (GEN III, GEN IV and fusion) and relative sensitivity analysis, as well through RAVEN, developed at INL. He is involved, in collaboration with ENEA, in the validation of such codes in liquid metals and the developing of a fusion version of RELAP5/mod 3.3 (for liquid metals and helical coil steam generators) and is a member of EU DEMO WCLL Breeding Blanket and Balance of Plant design team and ITER WCLL Water Cooling System for the Test Blanket System design team. He is also involved, in collaboration of Idaho National Laboratory (USA), in the validation of PHISICS/RELAP5-3D NK-TH coupled code for fast reactors mainly through the IAEA CRP Benchmark Analysis of FFTF Loss Of Flow Without Scram Test.


nuclear thermal hydraulics
Thermal-hydraulic transient analysis
nuclear fusion reactor
Fast neutron reactors
fusion reactor blanket
balance of plant
3D coupled dynamic analysis
Gen-IV lead cooled fast reactors
nuclear accidents

Gruppi di ricerca

Laboratori di ricerca

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