Cristiano Ciurluini | Ricerc@Sapienza

Pubblicazioni

Titolo	Pubblicato in	Anno
Pre-test analysis and thermal-hydraulic characterization of the versatile loop facility	NUCLEAR ENGINEERING AND DESIGN	2025
A systematic approach for the adequacy analysis of a set of experimental databases. Application in the framework of the ATRIUM activity	NUCLEAR ENGINEERING AND DESIGN	2024
RELAP5/Mod3.3 thermal-hydraulics characterization of the steam generator mock-up during operational transients in STEAM facility in support of the design of the DEMO WCLL BoP	FUSION ENGINEERING AND DESIGN	2024
Pre-test analysis of low power operations of STEAM, the EU-DEMO steam generator mock-up facility	FUSION ENGINEERING AND DESIGN	2024
RELAP5-based thermal-hydraulic assessment of the STEAM facility for DEMO WCLL balance of plant analysis	FUSION ENGINEERING AND DESIGN	2024
Conceptual design and supporting analysis of a double wall heat exchanger for an ARC-class fusion reactor Primary cooling system	FUSION ENGINEERING AND DESIGN	2024
System code simulation of DEMO WCLL central outboard blanket equatorial cell operational transients	FUSION ENGINEERING AND DESIGN	2024
Analysis of Steady State and Operational Transients of the Versatile Loop Facility in support to Lead Fast Reactor development	Proceeding of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)	2024
Investigation of the fast flux test facility transient behavior during a loss of flow without scram test	NUCLEAR ENGINEERING AND DESIGN	2024
Assessment of the relevancy of ENEA water loop facility with respect to ITER WCLL TBS water cooling system by considering their thermal-hydraulic performances	FUSION 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
Performance evaluation of a coupled CFX-RELAP5 tool adopting experimental data from the TALL-3D facility	NUCLEAR ENGINEERING AND DESIGN	2024
Design and integration of the EU-DEMO water-cooled lead lithium breeding blanket	ENERGIES	2023
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
Development of a Steam Generator Mock-Up for EU DEMO Fusion Reactor: Conceptual Design and Code Assessment	ENERGIES	2023
Subchannel modelling capabilities of RELAP5-3D© for wire-spaced fuel pin bundle	NUCLEAR ENGINEERING AND DESIGN	2023
Subchannel Analysis of LFR Wire-Wrapped Fuel Bundle with RELAP5-3D	NUCLEAR TECHNOLOGY	2023
The STEAM Facility: Design and Analysis	Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)	2023
Status, Design and Thermal-Hydraulic Analyses of the Steam Facility for DEMO WCLL Balance of Plant Systems	Proceedings of the 2023 30th International Conference on Nuclear Engineering ICONE30	2023

ERC

PE8_6

KET

Big data & computing

Interessi di ricerca

Thermal-hydraulic analysis of fission and fusion reactors. Studies are both design-oriented and aimed at investing the system performances during operational and accidental conditions.

Keywords

nuclear accidents

fusion reactor blanket

Fission energy

Thermal-hydraulic transient analysis

Numerical Analysis

Progetti di Ricerca

Detailed thermal-hydraulic study of the EU-DEMO Water Cooled Lithium-Lead Breeding Blanket elementary cell
Thermal-hydraulic analysis of the EU-DEMO WCLL Breeding Blanket systems during a Loss Of Flow Accident
Neutron kinetic and Thermal-hydraulic coupled analisys of FFTF reactor Unprotected Loss of Flow transient

Gruppi di ricerca

NERG - Nuclear Engineering Research Group