Fabio Giannetti


Titolo Pubblicato in Anno
Investigation on RELAP5-3D© capability to predict thermal stratification in liquid metal pool-type system and comparison with experimental data NUCLEAR ENGINEERING AND DESIGN 2019
System thermal-hydraulic modelling of the phénix dissymmetric test benchmark NUCLEAR ENGINEERING AND DESIGN 2019
MYRRHA primary heat exchanger experimental simulations on CIRCE-HERO NUCLEAR ENGINEERING AND DESIGN 2019
Post-test simulations for the NACIE-UP benchmark by STH codes NUCLEAR ENGINEERING AND DESIGN 2019
Experimental analysis of stationary and transient scenarios of ALFRED steam generator bayonet tube in CIRCE-HERO facility NUCLEAR ENGINEERING AND DESIGN 2019
Post-test simulation of a PLOFA transient test in the CIRCE-HERO facility NUCLEAR ENGINEERING AND DESIGN 2019
A Preliminary Exergy Analysis of the EU DEMO Fusion Reactor TECNICA ITALIANA 2019
Characterization of leak detection in HLM system using LIFUS5/MOD3 facility 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 2019
Advancements in DEMO WCLL breeding blanket design and integration INTERNATIONAL JOURNAL OF ENERGY RESEARCH 2018
Recent progress in the WCLL breeding blanket design for the DEMO fusion reactor IEEE TRANSACTIONS ON PLASMA SCIENCE 2018
GEN-IV LFR development: Status & perspectives PROGRESS IN NUCLEAR ENERGY 2018
Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket FUSION ENGINEERING AND DESIGN 2018
Study of EU DEMO WCLL breeding blanket and primary heat transfer system integration FUSION ENGINEERING AND DESIGN 2018
Pre-test analysis of accidental transients for ALFRED SGBT mock-up characterization NUCLEAR ENGINEERING AND DESIGN 2018
Design and analysis of a new configuration of secondary circuit of the EU-DEMO fusion power plant using GateCycle FUSION ENGINEERING AND DESIGN 2018
Phénix transient analysis for the assessment of RELAP5-3D based on dissymmetric test benchmark International Conference on Nuclear Engineering, Proceedings, ICONE 2018
Sirio: An experimental facility for a new heat removal system passively controlled by non-condensable gases International Conference on Nuclear Engineering, Proceedings, ICONE 2018
Blind simulations of NACIE-UP experimental tests by STH codes 2018 26th International Conference on Nuclear Engineering 2018
Performance-based ECCS cladding acceptance criteria: A new simulation approach ANNALS OF NUCLEAR ENERGY 2017
Numerical study of laminar magneto-convection in a differentially heated square duct JOURNAL OF PHYSICS. CONFERENCE SERIES 2017


  • 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

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