Fabio Giannetti

Pubblicazioni

Titolo Pubblicato in Anno
WCLL breeding blanket design and integration for DEMO 2015: status and perspectives FUSION ENGINEERING AND DESIGN 2017
CFD analysis of WCLL BB PbLi manifold FUSION ENGINEERING AND DESIGN 2017
Analysis of the secondary circuit of the DEMO fusion power plant using GateCycle FUSION ENGINEERING AND DESIGN 2017
Improvements to PHISICS/RELAP5-3D© capabilities for simulating HTGRs Transactions of the American Nuclear SocietyTRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY 2017
Pool temperature stratification analysis in CIRCE-ICE facility with RELAP5-3D© model and comparison with experimental tests JOURNAL OF PHYSICS. CONFERENCE SERIES 2017
Pre-test analysis of protected loss of primary pump transients in CIRCE-HERO facility JOURNAL OF PHYSICS. CONFERENCE SERIES 2017
Analysis of unmitigated large break loss of coolant accidents using MELCOR code JOURNAL OF PHYSICS. CONFERENCE SERIES 2017
New phisics perturbation method module verification using the HTTR neutronic model TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY 2017
New RELAP5-3D Lead and LBE Thermophysical Properties Implementation for Safety Analysis of Gen IV Reactors SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2016
Thermal-hydraulic analysis of an innovative decay heat removal system for lead-cooled fast reactors NUCLEAR ENGINEERING AND DESIGN 2016
Enhanced shuffling and fuel management capability in PHISICS code Proceedings of the American Nuclear SocietyTRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY 2016
Sizing of the Vacuum Vessel Pressure Suppression System of a Fusion Reactor Based on a Water-Cooled Blanket, for the Purpose of the Preconceptual Design SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2016
An experimental study on the air-side heat transfer coefficient and the thermal contact conductance in finned tubes HEAT TRANSFER ENGINEERING 2015
Effects of cross sections library parameters on the OECD/NEA Oskarshamn-2 benchmark solution ANNALS OF NUCLEAR ENERGY 2015
Simulation tools and approaches for the compliance with performance-based ECCS cladding acceptance criteria (10 CFR50.46c) TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY 2015
A comprehensive validation approach using the RAVEN code TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY 2015

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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