| 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 |
