Fabio Giannetti

Pubblicazioni

Titolo Pubblicato in Anno
Analysis of the thermal-hydraulic behavior of the EU-DEMO WCLL breeding blanket cooling systems during a loss of flow accident FUSION ENGINEERING AND DESIGN 2021
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System FUSION ENGINEERING AND DESIGN 2021
Total loss of flow benchmark in CIRCE-HERO integral test facility NUCLEAR ENGINEERING AND DESIGN 2021
Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges FUSION ENGINEERING AND DESIGN 2021
Development of a PbLi heat exchanger for EU DEMO fusion reactor: Experimental test and system code assessment FUSION ENGINEERING AND DESIGN 2021
Preliminary design of a helical coil steam generator mock-up for the CIRCE facility for the development of DEMO LiPb heat exchanger FUSION ENGINEERING AND DESIGN 2021
Conceptual design overview of the ITER WCLL Water Cooling System and supporting thermal-hydraulic analysis FUSION ENGINEERING AND DESIGN 2021
Design and optimization of the secondary circuit for the WCLL BB option of the EU-DEMO power plant FUSION ENGINEERING AND DESIGN 2021
Study of the EU-DEMO WCLL breeding blanket primary cooling circuits thermal-hydraulic performances during transients belonging to LOFA category ENERGIES 2021
Experimental investigation on circe-hero for the eu demo pbli/water heat exchanger development ENERGIES 2021
Preliminary uncertainty quantification of the core degradation models in predicting the Fukushima Daiichi unit 3 severe accident NUCLEAR ENGINEERING AND DESIGN 2021
Thermal-hydraulic transient analysis of the FFTF LOFWOS Test #13 NUCLEAR ENGINEERING AND DESIGN 2021
Development of a RELAP5/MOD3.3 module for MHD pressure drop analysis in liquid metals loops. Verification and validation ENERGIES 2021
Improvements of RELAP5/Mod3.3 heat transfer capabilities for simulation of in-pool passive power removal systems ANNALS OF NUCLEAR ENERGY 2021
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

ERC

  • PE8_6

KET

  • 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.

Keywords

nuclear thermal hydraulics
Thermal-hydraulic transient analysis
SEVERE ACCIDENT
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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