Salta al contenuto principale
Ricerc@Sapienza
Toggle navigation
Home
Login
Home
Persone
vincenzo.narcisi@uniroma1.it
Vincenzo Narcisi
Assegnista di ricerca
Struttura:
DIPARTIMENTO DI INGEGNERIA ASTRONAUTICA, ELETTRICA ED ENERGETICA
E-mail:
vincenzo.narcisi@uniroma1.it
Pagina istituzionale corsi di laurea
Curriculum Sapienza
Pubblicazioni
Titolo
Pubblicato in
Anno
Investigation of the fast flux test facility transient behavior during a loss of flow without scram test
NUCLEAR ENGINEERING AND DESIGN
2024
OECD/NEA/CSNI/WGAMA PERSEO benchmark: Main outcomes and conclusions
NUCLEAR ENGINEERING AND DESIGN
2023
Subchannel modelling capabilities of RELAP5-3D© for wire-spaced fuel pin bundle
NUCLEAR ENGINEERING AND DESIGN
2023
Analysis and Preliminary Design of Primary Heat Exchanger Failure Testing Facility for Lead-Cooled Fast Reactors
NUCLEAR TECHNOLOGY
2023
Transient analysis of SIRIO using RELAP5/MOD3.3 system code
JOURNAL OF PHYSICS. CONFERENCE SERIES
2023
Subchannel Analysis of LFR Wire-Wrapped Fuel Bundle with RELAP5-3D
NUCLEAR TECHNOLOGY
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
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
Thermal hydraulic transient analysis of ITER safety-relevant secondary cooling water system
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
Development of a PbLi heat exchanger for EU DEMO fusion reactor: Experimental test and system code assessment
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
Experimental investigation on circe-hero for the eu demo pbli/water heat exchanger development
ENERGIES
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
1
2
seguente ›
ultima »
Progetti di Ricerca
Uncertainty quantification in RELAP5-3D© simulation of NACIE experimental facility focused on code validation
© Università degli Studi di Roma "La Sapienza" - Piazzale Aldo Moro 5, 00185 Roma