Cristiano Ciurluini | Ricerc@Sapienza

Pubblicazioni

Titolo	Pubblicato in	Anno
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
Transient analysis of a locked rotor/shaft seizure accident involving the EU-DEMO WCLL Breeding Blanket primary cooling circuits	FUSION ENGINEERING AND DESIGN	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
Analysis of the thermal-hydraulic behavior of the EU-DEMO WCLL breeding blanket cooling systems during a loss of flow accident	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
Conceptual design overview of the ITER WCLL Water Cooling System and supporting thermal-hydraulic analysis	FUSION ENGINEERING AND DESIGN	2021
Study of the EU-DEMO WCLL breeding blanket primary cooling circuits thermal-hydraulic performances during transients belonging to LOFA category	ENERGIES	2021
Thermal-hydraulic transient analysis of the FFTF LOFWOS Test #13	NUCLEAR ENGINEERING AND DESIGN	2021
Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module	FUSION ENGINEERING AND DESIGN	2020
Preliminary neutron kinetic. Thermal hydraulic coupled analysis of the ALFRED reactor using PHISICS/RELAP5-3D	JOURNAL OF PHYSICS. CONFERENCE SERIES	2020
Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code	FUSION ENGINEERING AND DESIGN	2019

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