Fabio Giannetti

Publications

Title Published on Year
The STEAM Facility: Design and Analysis Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) 2023
Status, Design and Thermal-Hydraulic Analyses of the Steam Facility for DEMO WCLL Balance of Plant Systems Proceedings of the 2023 30th International Conference on Nuclear Engineering ICONE30 2023
STEAM experimental facility. A step forward for the development of the EU DEMO BoP Water Coolant Technology ENERGIES 2023
The design of water loop facility for supporting the WCLL breeding blanket technology and safety ENERGIES 2023
PbLi/Water Reaction: Experimental Campaign and Modeling Advancements in WPBB EUROfusion Project ENERGIES 2023
IAEA'S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS International Conference on Nuclear Engineering, Proceedings, ICONE 2023
Preliminary MHD pressure drop analysis for the prototypical WCLL TBM with RELAP5/MOD3.3 FUSION ENGINEERING AND DESIGN 2022
Tokamak cooling systems and power conversion system options FUSION ENGINEERING AND DESIGN 2022
Maturation of critical technologies for the DEMO balance of plant systems FUSION ENGINEERING AND DESIGN 2022
Dynamic event tree analysis as a tool for risk assessment in nuclear fusion plants using RAVEN and MELCOR IEEE TRANSACTIONS ON PLASMA SCIENCE 2022
Analysis of EU-DEMO WCLL Power Conversion System in Two Relevant Balance of Plant Configurations: Direct Coupling with Auxiliary Boiler and Indirect Coupling SUSTAINABILITY 2022
Transient analysis of OSU-MASLWR with RELAP5 JOURNAL OF PHYSICS. CONFERENCE SERIES 2022
Evaluation of the thermal-hydraulic performances of a once-through steam generator in nuclear fusion applications JOURNAL OF PHYSICS. CONFERENCE SERIES 2022
Analysis of Fukushima Daiichi unit 4 spent fuel pool using MELCOR JOURNAL OF PHYSICS. CONFERENCE SERIES 2022
Severe accident sensitivity and uncertainty estimation using MELCOR and RAVEN JOURNAL OF PHYSICS. CONFERENCE SERIES 2022
Decontamination and remediation of underground holes and testing of cleaning techniques based on the use of liquid cold decontaminant SUSTAINABILITY 2022
CFD Analysis and Optimization of the DEMO WCLL Central Outboard Segment Bottom-Cap Elementary Cell JOURNAL OF NUCLEAR ENGINEERING 2022
Transient analysis of a locked rotor/shaft seizure accident involving the EU-DEMO WCLL Breeding Blanket primary cooling circuits FUSION ENGINEERING AND DESIGN 2022
ATHENA MAIN HEAT EXCHANGER CONCEPTUAL DESIGN AND THERMAL-HYDRAULIC ASSESSMENT WITH RELAP5 CODE International Conference on Nuclear Engineering, Proceedings, ICONE 2022
STEAM: a novel experimental infrastructure for the development of the DEMO BOP water coolant technology 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19) 2022

ERC

  • PE8_6

KET

  • Big data & computing
  • Sustainable technologies & development

Interessi di ricerca

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

Progetti di Ricerca

Gruppi di ricerca

NERG - Nuclear Engineering Research Group

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