Fabio Giannetti | Ricerc@Sapienza

Publications

Title	Published on	Year
A novel ansys CFX – RELAP5 coupling tool for the transient thermal-hydraulic analysis of liquid metal systems	PROGRESS IN NUCLEAR ENERGY	2025
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package	ANNALS OF NUCLEAR ENERGY	2025
Pre-test analysis and thermal-hydraulic characterization of the versatile loop facility	NUCLEAR ENGINEERING AND DESIGN	2025
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
An OpenFOAM multi-region solver for tritium transport modeling in fusion systems	FUSION ENGINEERING AND DESIGN	2024
RELAP5-based thermal-hydraulic assessment of the STEAM facility for DEMO WCLL balance of plant analysis	FUSION ENGINEERING AND DESIGN	2024
System code simulation of DEMO WCLL central outboard blanket equatorial cell operational transients	FUSION ENGINEERING AND DESIGN	2024
Analysis of Steady State and Operational Transients of the Versatile Loop Facility in support to Lead Fast Reactor development	Proceeding of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)	2024
Investigation of the fast flux test facility transient behavior during a loss of flow without scram test	NUCLEAR ENGINEERING AND DESIGN	2024
Assessment of the relevancy of ENEA water loop facility with respect to ITER WCLL TBS water cooling system by considering their thermal-hydraulic performances	FUSION ENGINEERING AND DESIGN	2024
Development and Optimization Criteria of Cementitious Mortars Used for the Immobilization of ILW Radioactive Waste	2024 31st International Conference on Nuclear Engineering - Volume 8: Decontamination and Decommissioning, Radiation Protection, and Waste Management	2024
Analysis of the experimental tests performed at NACIE-UP facility through a novel CFX-RELAP5 codes coupling	NUCLEAR ENGINEERING AND DESIGN	2024
Loss-of-heat-sink transient simulation with RELAP5/Mod3.3 code for the ATHENA facility	ANNALS OF NUCLEAR ENERGY	2024
Performance evaluation of a coupled CFX-RELAP5 tool adopting experimental data from the TALL-3D facility	NUCLEAR ENGINEERING AND DESIGN	2024
Re-scaling and Pre-test Analysis of SIRIO facility	41th UIT International Heat Transfer Conference	2024
Coupled CFD-STH modelling of the ATHENA lead-cooled pool-type facility	14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-14)	2024
Loss-of-Heat-Sink Transient Simulation with RELAP5/Mod3.3 Code for the ATHENA Facility	14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-14)	2024

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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

Experimental evaluation of pool boiling heat transfer coefficient at high thermal flux for a passive decay heat removal system to be used in fission and fusion power plant
RELAP5-3D© code validation for pool temperature stratification analysis in heavy liquid metal reactor by comparison with CIRCE-ICE experimental data
Development and validation of a thermal-hydraulic model of helical coil liquid metal steam generators for design and safety analyses of innovative fission and fusion nuclear plants
Development and validation of a thermal-hydraulic transient model capable to analyze the TBM for ITER and the Breeding Blanket for the EU-DEMO reactor

Gruppi di ricerca

NERG - Nuclear Engineering Research Group

Laboratori di ricerca

Laboratorio di Calcolo per la Didattica