| 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 |
