Tommaso Del Moro | Ricerc@Sapienza

Pubblicazioni

Titolo	Pubblicato in	Anno
A novel ansys CFX – RELAP5 coupling tool for the transient thermal-hydraulic analysis of liquid metal systems	PROGRESS IN NUCLEAR ENERGY	2025
Development of a thermal mass flow meter for heavy liquid metal applications	NUCLEAR ENGINEERING AND DESIGN	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
Conceptual Design of the Steam Generators for the EU DEMO WCLL Reactor	ENERGIES	2023
Thermal-hydraulic assessment of Once-Through Steam Generators for EU-DEMO WCLL Breeding Blanket primary cooling system application	FUSION ENGINEERING AND DESIGN	2023
Thermal-Hydraulic Characterization and Numerical Modeling with RELAP5 Code of ATHENA Secondary Loop	NUCLEAR TECHNOLOGY	2023
ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code	JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE	2023
Post-Test Analysis of SIRIO Facility Data by System Thermal-Hydraulic Codes for LFR Application	Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)	2023
Numerical Analysis and Codes Qualification Based on SIRIO Experiments Within the PIACE Project	Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)	2023
CFD - STH Code Coupling for the Thermal Hydraulic Analysis of NACIE-UP Experimental Facility	Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)	2023
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
ATHENA Integral Test Facility: Secondary System Design and Thermal-Hydraulic Assessment with RELAP5 Code	The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 13)	2022

Gruppi di ricerca

NERG - Nuclear Engineering Research Group