Fabio Giannetti


Titolo Pubblicato in Anno
The DEMO water-cooled lead–lithium breeding blanket: design status at the end of the pre-conceptual design phase APPLIED SCIENCES 2021
Design and Development of a package prototype for intermediate level solid waste (ILW) HAZARDOUS WASTE 2021
Preliminary safety analysis of an in-vessel LOCA for the EU-DEMO WCLL blanket concept FUSION ENGINEERING AND DESIGN 2020
RELAP5-3D three-dimensional analysis based on Phénix dissymmetric transient test JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2020
Preliminary evaluation of ALFRED revised concept under station blackout NUCLEAR ENGINEERING AND DESIGN 2020
Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module FUSION ENGINEERING AND DESIGN 2020
Preliminary sensitivity analysis for an ex-vessel LOCA without plasma shutdown for the EU DEMO WCLL blanket concept FUSION ENGINEERING AND DESIGN 2020
Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor FUSION ENGINEERING AND DESIGN 2020
Preliminary neutron kinetic. Thermal hydraulic coupled analysis of the ALFRED reactor using PHISICS/RELAP5-3D JOURNAL OF PHYSICS. CONFERENCE SERIES 2020
On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances FUSION ENGINEERING AND DESIGN 2020
Experimental characterization of leak detection systems in HLM pool using LIFUS5/Mod3 facility NUCLEAR TECHNOLOGY 2020
Assessment of relap5-3d for application on in-pool passive power removal systems Proceedings of the 30th European Safety and Reliability Conference and the 15th Probabilistic Safety Assessment and Management Conference 2020
Numerical analysis of temperature stratification in the CIRCE pool facility JOURNAL OF PHYSICS. CONFERENCE SERIES 2019
MHD mixed convection flow in the WCLL: heat transfer analysis and cooling system FUSION ENGINEERING AND DESIGN 2019
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion Project FUSION ENGINEERING AND DESIGN 2019
Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code FUSION ENGINEERING AND DESIGN 2019
In-box LOCA accident analysis for the European DEMO water-cooled reactor FUSION ENGINEERING AND DESIGN 2019
Uncertainty quantification method for RELAP5-3D© using RAVEN and application on NACIE experiments ANNALS OF NUCLEAR ENERGY 2019
Steam Generator mock-up preliminary design suitable for Pb-Li technology demonstration and code assessment FUSION ENGINEERING AND DESIGN 2019
Design and analysis of the improved configuration of the secondary circuit for the EU-DEMO power plant FUSION ENGINEERING AND DESIGN 2019


  • 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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